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Reactor Safety

Reactor Safety

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Reactor safety is the field of study focused on ensuring the safe operation of nuclear reactors. It encompasses the assessment, management, and mitigation of risks associated with nuclear fission processes, including the design of safety systems, emergency preparedness, and regulatory compliance to protect public health and the environment from potential hazards.
lightbulbAbout this topic
Reactor safety is the field of study focused on ensuring the safe operation of nuclear reactors. It encompasses the assessment, management, and mitigation of risks associated with nuclear fission processes, including the design of safety systems, emergency preparedness, and regulatory compliance to protect public health and the environment from potential hazards.

Key research themes

1. How do statistical analyses and historical data inform the understanding and quantification of nuclear power accident risks?

This research area focuses on utilizing comprehensive datasets of nuclear accidents and incidents to statistically characterize the frequency, severity, and cost implications of nuclear power plant failures. The goal is to provide a quantitative foundation for risk management, surpassing traditional probabilistic safety analyses and qualitative scales such as INES. This approach informs policy and safety reforms by quantifying the likelihood and economic magnitude of extreme nuclear accidents.

Reassessing the safety of nuclear power
by Benjamin Sovacool

2019

Key finding: Derived from a dataset of 216 nuclear events (twice the size of prior datasets), the study statistically estimates that with 388 reactors operational, there is a 50% probability of an accident comparable to Fukushima... Read more
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Source Term Assessment for 100 Mwe Pressurized Water Reactor
by M. Budi Setiawan

2023, JURNAL TEKNOLOGI REAKTOR NUKLIR TRI DASA MEGA

Key finding: Provides a data-driven source term evaluation of a small modular PWR under normal and Design Basis Accident (DBA) conditions, leveraging prior PWR-1000MWe data and fuel failure fractions. The study quantifies radionuclide... Read more
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Environmental Consequences of Routine Releases from Small Medium Reactor at Babel Site
by M. Budi Setiawan

2023, JURNAL TEKNOLOGI REAKTOR NUKLIR TRI DASA MEGA

Key finding: Quantitatively analyzes radiological consequences of routine radioactive releases from triple 100 MWe PWR units using site-specific meteorological and geographical data. Using ORIGEN2 for source term estimation and PC-CREAM... Read more
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2. What are the advances and challenges in designing and regulating next-generation nuclear reactors emphasizing safety improvements?

This theme encompasses the development, evaluation, and regulatory evolution of innovative nuclear reactor designs, including Gen IV Sodium-Cooled Fast Reactors, small modular reactors (SMRs), and molten salt reactors. Key focuses include enhancing inherent safety characteristics, passive safety features, managing severe accidents, and integrating lessons learned from past events (e.g., Fukushima). Additionally, this area addresses the regulatory frameworks and legal structures required to support safe deployment and operation.

Overall System Description and Safety Characteristics of Prototype Gen IV Sodium Cooled Fast Reactor in Korea
by Jonghwa Chang

2024, Nuclear Engineering and Technology

Key finding: Summarizes the development and safety design features of Korea's Prototype Gen IV sodium cooled fast reactor (PGSFR). The design emphasizes robust inherent safety through metal fuel, passive safety via natural circulation and... Read more
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Preliminary occupational radiation exposure evaluation related to NET II/ITER
by sandro sandri

2025, 15th IEEE/NPSS Symposium. Fusion Engineering

Key finding: Presents an early occupational radiation exposure (ORE) assessment methodology for maintenance activities in the tritium and tokamak buildings of the NET/ITER fusion plant. It integrates prompt radiation, activation product... Read more
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Legal and Regulatory Development of Nuclear Energy in Bangladesh
by Ridoan Karim

2022, Energies

Key finding: Employs analytical heat transfer modeling to design an Emergency Draining Tank (EDT) system for the Molten Salt Fast Reactor, ensuring passive fuel salt drainage and long-term safe cooling under decay heat load. The study... Read more
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Legal and Regulatory Development of Nuclear Energy in Bangladesh
by Ridoan Karim

2022, Energies

Key finding: Complementing the prior entry, this work highlights the use of hexagonal cooling assemblies filled with inert materials to passively dissipate decay heat from drained fuel salt. It focuses on ensuring fuel remains liquid and... Read more
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Legal and Regulatory Development of Nuclear Energy in Bangladesh
by Ridoan Karim

2022, Energies

Key finding: Proposes a novel quantitative methodology named 'safeometrics' inspired by chemometrics, aimed at advancing the quantitative safety analysis framework across industries including nuclear power. It advocates for rigorous... Read more
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Legal and Regulatory Development of Nuclear Energy in Bangladesh
by Ridoan Karim

2022, Energies

Key finding: Evaluates recent legislative and regulatory progress underpinning nuclear energy deployment in Bangladesh, highlighting achievements and gaps in the legal infrastructure ensuring nuclear safety, security, and liability... Read more
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3. How can radioactive corrosion products and nuclear waste be effectively adsorbed, immobilized, and managed to enhance reactor safety?

This research theme addresses the development of advanced materials and techniques for the removal and immobilization of radioactive ionic corrosion products generated during nuclear reactor operation. Effective management of such radioactive contaminants is crucial to reduce radiation exposure risks to workers and the environment, extend component lifespan, and ensure the safety of nuclear facilities and waste repositories.

Adsorption and immobilization of radioactive ionic-corrosion- products using magnetic hydroxyapatite and cold-sintering for nuclear waste management applications
by Muhmood ul Hassan

2018, Journal of Nuclear Materials

Key finding: Developed a magnetically assisted hydroxyapatite nanocomposite (MA-HAP) that demonstrated high adsorption capacity (68.95 mg/g for Co2+) for radioactive ionic corrosion products under optimized conditions (pH 6, 120 min... Read more
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Related Topics

  • Reactor physics (Physics)
  • Reactor Design
  • Reactor Safety Analysis
  • Radioactive waste management
  • Nuclear Fuel Cycle
  • Nuclear Materials
  • Advanced Reactor Design
  • Advanced Nuclear Energy Systems
  • Nuclear Criticality Safety
  • Fuel Cell Engineering

    • All papers in Reactor Safety

    Knowledge, belief, and attitude of Bangladeshi youth toward the development of nuclear power
    by abid khan

    2024, Nuclear Energy and Technology

    Public support is one of the major challenges for maintaining a sustainable nuclear power program for any country. Although Bangladesh's decision to build its maiden nuclear power plant (NPP) has received significant scholarly attention,... more
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    Analytical investigation of the draining system for a molten salt fast reactor
    by Shisheng Wang

    2024

    Molten Salt Fast Reactor (MSFR) is a conceptual design by European Union that contains a draining tank located underneath the reactor. In case of a planned reactor shut down or in emergency situations or in case of accidents leading to an... more
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    Natural Convection Heat Transfer in Two-Fluid Stratified Pools with Internal Heat Sources
    by Askar GUBAIDULLIN

    2024

    Natural convection is a subject of interest in fundamental fluid dynamics and heat transfer, as well as in a great number of engineering applications. In particular, knowledge of thermal convection driven by internal heat sources is of... more
    Figure 4.29: Dimensionless mean eddy heat transport. Figure 4.30: Production of thermal vari- ance 7”.
    Figure 4.19: Visual observation of the pool melting at steady state (SIMECO test SNEu-03. Ref. [601). Figure 4.20: Velocity field, crust and mushy zone front for Ra; = 1.4- 10°.
    Figure 4.23: Velocity field (Ra = 2- 10°).
    Figure 1.1: Schematic of the IVMR.
    The conservation equations for fluid 1 are Continuity of temperature, velocity, heat flux and shear stresses must be satisfied at the fluid-to-fluid interface. Continuity of heat flux gives the dimensionless group K4Q >= ky /ko. Here, Gry (or Ray) is defined on the reference values of fluid 2 and on the tem- perature difference (7 — T,). So the investigation of the two-layer problem becomes significantly more complicated.
    Circular and spherical cavities. Mayinger et al. [74] were the first to report ex- perimental and computational results for thermal convection in volumetrically-heated semicircular pools. In the last decade, a number of research programs have appeared world-wide: USA (UCLA facility, [1], ACOPO at UCSB, [108]), Russia (OECD RAS- PLAV project, [2]), France (BALI, [11]), Finland (COPO, [70]), and Sweden (FOR- EVER, [94], SIMECO, [93]). The main objective of these tests is to obtain the heat transfer characteristics applicable to prototypical configurations and simulants. The heat transfer correlations for different geometries (Figs. 2.2) are summarized in Tables 2.4-2.5 below.
    Chapter 3. Analytical Study Figure 3.1: Semiempirical (dashed lines) and experimental (solid lines) Nusselt num. ber as a function of the Rayleigh number for Heptane- Water.
    Figure 3.5: Nusselt number dependence on kinematic viscosity ratio (£12 = 0.1). Figure 3.4: Nusselt number dependence on conductivity ratio (L12 = 0.1). Figure 3.3: Nusselt number dependence on height ratio (kg = 0.2). Here, we plot Nu as a function of Ly9 for fixed values of the other parameters. It can be seen in Fig. 3.3 that the effect of depth ratio is weak for 0.01 < Lig < 0.1. Nu becomes greater as [Lj increases for L;2 > 0.1. The correlation is similar to the behaviour observed experimentally for Nu as Lyj9 is varied. The analysis cannot be applied for Ly2 < 1, when capillary forces and other effects must be taken into account. the behaviour observed experimentally for Nu as Ly is varied. The analysis cannot
    Thus, we have obtained the equation for 7 as a function of the following six di- mensionless parameters: Rag, Prj, 12, Lig, 12,12, 12. AS a result, investigation of this problem becomes substantially more complicated than for the one-fluid case. The equation 3.20 can be solved numerically. The values of 7 as a function of Rag are plotted in Fig. 3.8. It can be seen that more heat is being transferred downwards in a double-layer configuration as the upper layer imposes additional thermal resistance. As Rag increases, the difference in 7 between one- and two-layer cases decreases.
    Figure 3.10: Dependence of the fraction of heat transfer downwards on k 19. Figure 3.10: Dependence of the fraction Figure 3.8: Dependence of the fraction of heat transfer downwards on Rag.
    Figure 3.9: Dependence of the fraction of heat transfer downwards on Ly9.
    Figure 3.11: Dependence of the fraction of heat transfer downwards on 119.
    The simulations were performed with the individual layer Rayleigh number ranging from 104 to 10’. The computed Nusselt numbers are presented in the reduced form given by Eq. 2.18, and compared to the correlation Eq. 2.20 suggested by Haberstroh and Reinders [46]. It can be seen that the computed results agree well with the predicted ones.
    Figure 4.2: Computed isotherms.
    Figure 4.3: Mean dimensionless temperature distribution along the height of the do- main
    Figure 4.4: Schematic of computational domain adjacent to the interface. The fixed interface two-fluid model is implemented into the code by means of the code’s user FORTRAN routines. The flow domain is divided in two sub-domains cou- pled through the boundary conditions at the interface. At each time step n+ 1 and each iteration, temperature and velocity at ¢-node at fluid-fluid interface (the upper boundary for fluid 2 and the lower boundary of fluid 1 as it is depicted in Fig. 4.4) are approxi- mated from the continuity of shear stress and heat flux as:
    Figure 4.5: a) Computed velocity field. b) Velocity distribution along y-axis. is equal to the analytical value of Ujnz = <qeee = 4/6 m/s. In the same way, heat transfer across the interface was checked for the conduction problem of two fluids having different conductivities.
    Figure 4.9: Temperature field (Raj = 10°, Lig = 6 : 26). Figure 4.8: Velocity field (paraffin oil- water).
    Figure 4.10: Computed isotherms for Rag = 2-10°, Lig = 8: 18, Qu, = Quy. 1.3 Computations with a double-diffusion model
    Figure 4.12: Problem formulation and boundary conditions employed for model vali- dation Here, for the purpose of the model validation, the numerical simulation of stepwise density stratification in a fluid layer with lateral heating is performed. The results are compared to those reported in [21]. Here, for the purpose of the model validation, the numerical simulation of stepwise
    Figure 4.14: The local Nusselt number distribution at For = 0.1
    Figure 4.15: Velocity field, crust and mushy zone front (t = 1000)
    Figure 4.16: Average Nusselt number Nw, variation with T* &C' (left) and Ra, (right).
    Table 4.3: Calculated results against the predictions of a semiempirical correlation by ~ 3 ». FF
    Figure 4.18: Temperature field (left) and mushy zone front (right) for TS = 0.058 with the correlation of Baker. The results are given in Table 4.3 below. The computed temperature field and mushy zone front are shown in Fig. 4.18.
    Figure 4.22: Temperature field (Ra = 2- 10°).
    Figure 4.26: Dimensionless mean temperature distribution.
    Figure 4.24: Dimensionless mean eddy heat transport. Figure 4.25: Production of thermal vari- ance 7”.
    Figure 4.21: Isotherms and mushy layer front for Ra; = 1.4 - 10°: no phase-change (left) and solidification (right).
    on Pr agrees with the trend given by the Globe & Dropkin [40] correlation. It should be noted that the values given by different correlations might have as great as nearly 40% difference for the Rayleigh number under consideration. At high Rayleigh numbers, the difference can be of a factor two or even larger. Mean temperature profiles for different values of Pr are plotted in Fig. 4.52. The values in the core are similar, and the difference near the boundaries is due to the differences in the thickness of the thermal boundary layer.
    Figure 4.34: Temperature fluctuations iT field (Ra = 4- 10°, Pr = 0.6).
    Figure 4.35: Temperature fluctuations 7 field (Ra = 4- 10°, Pr =6).
    Figure 4.38: Dimensionless production and dissipation of turbulent kinetic energy far differant racac (Pn —9 AV INT) Figure 4.36: Dimensionless T;,,,, (Ra = Fig 2.4 x 10°). 2.4
    Figure 4.37: (Dimensionless v;,; Ra = 2.4 x 10°).
    Figure 4.39: Production of thermal vari- ance 7"? for different cases (Ra = 2.4 x 10°).
    Figure 4.42: Turbulent viscosity (Ra = 2.4 x 10", Pr = 6).
    ‘igure 4.40: Dimensionless mean tem-
    (Ra = 2.4 x 10°).
    Figure 4.43: The flux Richardson number (Ra = 2.4 x 10’, Pr = 6).
    Figure 4.45: Vertical profile of the horizontally-averaged temperature (Ra = 6.3 x 10°. Pr = 0.71).
    Figure 4.44: Computed temperature field at z=0.5 (Ra = 6.3 x 10°, Pr = 0.7).
    Figure 4.46: Variation of reduced mean temperature profiles for different Prandtl numbers (Ra = 63 x 10°).
    Figure 4.49: Vertical profile of dimen- sionless Upm; (Ra = 6.3 x 10°,Pr = 0.71). Figure 4.49: Vertical profile of dimen-
    Figure 4.50: Vertical profiles of terms in the thermal variance equation (Ra = 6.3 x 41N5 N.. nwt.
    Figure 4.48: Vertical profile of dimen- sionless Upms (Ra = 6.3 x 10°,Pr = 0.71).
    Figure 4.51: Vertical profile of Nus- selt numbers for different Prandtl numbers (Ra = 6.3 x 10°).
    Figure 4.52: Vertical profile of dimen- sionless centerline temperatures for differ- segs Wess ce ee) eeeeedccres fT . & BW ce TASS
    Figure 5.1: Schematic of the SIMECO experimental facility. Chapter 5. Experimental Study
    Figure 5.2: Main dimensions.
    Figure 5.3: Temperature field taken by infra-red camera.
    Figure 5.4: Post-test section. Figure 5.4 shows the post-test view of the solidified pool. The crust region can be distinguished from the molten region by its darker shade. The contact between he top heat exchanger and the pool was found to contain no gaps. However, due to shrinkage of the salt during its sudden solidification, after the top heat exchanger had been placed, a small air-gap can form, although it is unlikely to affect the thermal processes in the pool, since it is assumed that the boundary temperature for the molten pool is the liquidus temperature, T),;,, of the eutectic salt.
    Figure 5.5: The mean upward Nusselt number.
    similar tests with different stimulant materials, but without crust formation. Figure 5.6: Computed temperature field for a) Qin = 2KW, b) Qin = 2.8kW. 5.4 Low Temperature Tests
    Figure 5.7: Local side wall heat flux dis- tribution for Qj, = 2kW. Figure 5.8: Local side wall heat flux dis- tribution for Qj, = 2.8kW.
    Chapter 5. Experimental Study of the paraffin oil increases the interfacial boundary layer resistance. Also, the higher viscosity of the oil somewhat reduces the intensity of the motion above the boundary layer.
    Figure 5.10: Local downward heat flux distribution.
    Figure 5.12: Readings from thermocou- ples inside the side wall heat exchanger (test no.2). Figure 5.11: Energy balance (test no.2). Chapter 5. Experimental Study
    Figure 5.13: Readings from thermocouples inside the brass side wall (test no.2).
    Figure 5.14: Centerline temperature dis- tributions for Qin = 2 kW, Ly2 = 3: 27. Figure 5.15: Centerline temperature dis- tributions for Qin = 3 kW, Ly2 = 3 : 27. Figure 5.14: Centerline temperature dis- Table 5.3: Test Matrix (Glycerol/Cerrobend)
    Figure 5.16: Centerline temperature dis- tributions for Qin = 2 kW, Lio = 6: 27.
    Figure 5.17: Centerline temperature dis- tributions for Qin = 2 kW, Ly2 = 6 : 27. Chapter 5. Experimental Study
    Figure 5.19: Local heat flux distributions for Qin =2 kW, Dy = 6: 27. Figure 5.18: Local heat flux distributions for Qin =2 kW, Ly =3: 27.
    Figure 5.21: Local heat flux distributions for Qin = 3kW, Ly = 6: 27. Figure 5.20: Local heat flux distributions for On = 3kW, Ly = 3:27. Chapter 5. Experimental Study
    Figure 5.22: Local dimensionless heat flux distributions for Qj, = 2 kW, Lig = 3:27.
    Figure 5.24: Local dimensionless heat flux distributions for Qj, = 3 kW, Lig = 3: 27.
    Figure 5.23: Local dimensionless heat flux distributions for Qj, = 2 kW, Lig = &.97
    Figure 5.26: Computational mesh for a) [£12 = 3:27; b) Ly = 6:27. Chapter 5. Experimental Study
    Figure 5.29: Centerline temperature dis- tributions for Qin = 1.5 kW, Ly. = 3 : 27. Figure 5.28: Computed temperature field for L12 = 6:27, Qin = 2kKW: a) isothermal top boundary; b) adiabatic top boundary
    Figure 5.30: Centerline temperature dis- tributions for Qin = 1.5 kW, Ly. = 6: 27.
    Figure 5.37: Heat capacity as a function of temperature.
    Table 2.2: Correlations for internally-heated horizontal fluid layers with an adiabatic lower wall and an isothermal upper boundary, with L being the height and X being the length of the fluid layer. The first heat transfer measurements for turbulent thermal convection in a fluid bounded by two rigid isothermal planes of equal temperature were reported by Kulacki and Goldstein [65]. In their study, the volumetric energy source was provided by Joule heating. The fluid height was varied from 1.27 to 6.35 cm, and the length and depth of the channel were both 25.4 cm. Horizontally-averaged temperature profiles were de- termined optically. Heat transfer correlations for the upper and lower boundaries were obtained from 67 observations. From the empirical correlation, the critical Rayleigh
    Figure 5.31: Local heat flux distributions for Ly = 3:27.
    Figure 5.33: Dimensionless local heat flux distributions for [45 = 3 : 27.
    Chapter 5. Experimental Study
    Figure 5.35: Viscosity as a function of temperature.
    Figure 5.36: Thermal conductivity as a function of temperature.
    Table 2.1: Correlations for Rayleigh-Bénard convection.
    Table 2.3: Correlations for internally heated horizontal fluid layers with isothermal lower and upper boundaries. Experimental studies in a similar configuration were reported by Mayinger [74], Jahn and Reineke [54], Kulacki and Emara [64]. Table 2.3 summarizes the heat transfer correlations obtained from these investigations.
    Table 2.4: Correlations for internally-heated semicircular and spherical pools heat transfer correlations for different geometries (Figs. 2.2) are summarized in Tables
    Table 2.5: Correlations for internally-heated semicircular and spherical pools (contd). Numerical studies. The earliest two-dimensional (2D) simulations of thermal con- vection in rectangular enclosures with internal heat generation were performed in the early 1970s by Thirlby [104] Peckover and Hutchinson [82] and Jahn and Reineke [54]. Mayinger e¢ al. [74] predicted natural convection heat transfer in a hemispherical cavity.
    Table 3.1: The experimental Nusselt number correlations of Kulacki and Nguen [68] Table 3.2: Physical properties (taken at T’ = 30°C’)
    The internally and uniformly heated fluid is contained in a square cavity with adi- abatic top and bottom walls. The walls are kept at constant temperature equal to the solidus temperature. Such a configuration provides simplicity in analyzing computed results and is able to capture major features of convection heat transfer in the near- wall region of an internally heated pool. The main parameter of interest in this case is the energy split, i.e. the fraction of heat generated within the layer that is transferred downward. Calculations are first performed for a case of without phase change and the results in terms of energy split, 7, are found to agree well with the correlation of Baket et al. [4]. The calculations are performed for different values of T, Q based on reference value of volumetric heat generation and a fixed value of Ra; equal to 8.8 x10°. Di- mensionless parameter 16 is defined as (Thig — Tso1)/QyH 2. The value of C is taker equal to 10°.
    Table 4.4: Computed vs. experimental average Nusselt numbers.
    Table 5.1: Physical properties (taken at T’ = 250° C for NaNO3 — K.NOs3 and T = 80° C for Cerrobend). In this section, a series of experiments employing an eutectic salt and Cerrobend is described. Cerrobend is a low melting point metal alloy composed of bismuth, lead, tin and cadmium. The objective of these tests is to investigate the ’focusing effect” when a metallic layer is employed as the top layer in an integral manner. The properties of the materials employed are summarized in Table 5.1.
    Table 5.2: Test Matrix (VaNO3 — K NO3/Cerrobend) In the adiabatic case, due to higher temperature in the metallic layer, the crust becomes thinner and nearly uniform, and completely disappears on the upper side. Qualitatively, MVITA predicts the major trends in the molten pool. [In the adiabatic case, due to higher temperature in the metallic layer, the crust becomes
    Figures 5.29-5.30 plot time average centerline temperature distributions for Dyj2 = 3: 27 and Lig = 6 : 27, respectively. In contrast to salt-Cerrobend tests, the heat transfer in the two pools is coupled through the interface. Thus, any variation of con- ditions in the upper layer leads to changes in the temperature field in the lower pool. It can be seen that in the uniform pool the turbulent mixed region (i.e. the part of the pool with nearly uniform temperature distribution along centerline) is substantially larger than for pools with a metallic layer. A non-heat-generating upper layer imposes addi- tional thermal resistance. As a result, higher temperatures are reached in the core of the stratified pools than in the core of the uniform one.
    Table 5.4: Heat Transfer in the Metallic Layer (Glycerol-Cerrobend) the metallic region are caused by a small driving temperature difference between the bulk temperature of the metal layer and the side boundary temperature of the brass wall. In fact, temperature of the relatively thick (2.3 cm) side brass wall increase with angle ® and the difference between the coolant and the brass wall temperature can reach considerable values (up to 20% higher) at the region around the interface. Thus, the side boundary temperature for the metallic layer is higher than the coolant inlet temperature and the boundary temperature, strictly speaking, is not constant. In the salt-Cerrobend tests, when the crust is formed in the metallic layer, due to low coolant temperatures, the side boundary temperature is the melting point of Cerrobend and the inhomogeneous brass wall temperature distribution affects only crust thickness, and not thermal processes in the metallic layer.
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    Phenomena identification and ranking table for thermal-hydraulic phenomena during a small-break LOCA with loss of high pressure injection
    by 郁男 木下

    2024, Progress in Nuclear Energy

    Currently Appendix K of 10 CFR 50 is used in the United States to evaluate models for the emergency cooling systems of light-water reactors. To assure that these models are accurate enough to ensure that the cooling systems are... more
    Fig. 1. Schematic of reactor pressure during SBLOCA with loss of HPI. A small-break LOCA can generally be divided into five phases, which take place over a relatively large period of time. This is due to the very slow decrease in the reactor coolant system (RCS) pressure due to the location and small size of the break. These phases are illustrated in Fig. 1, which shows the pressure in the pressurizer during a small-break LOCA with a loss of High Pressure Injection (HPI). The first phase of the accident is the blowdown phase, which lasts less than one minute as shown in the figure. This is the onset of the accident, when the RCS pressure decreases rapidly as coolant inventory exits from the break. When the pressurizer low-pressure set point is reached, the reactor trips. At this time the steam generator is isolated by closing the steam dump valves to the condenser. The steam generator secondary side pressure then continues to increase until it reaches the set point of the main steam safety valves, which release steam to the environment to maintain safe pressure in the secondary side of the steam gener- ator. During this time the RCS pressure continues to fall until it reaches the low-low-pressure set point. When this occurs, the reactor coolant pumps begin to coastdown. High-pressure injection
    Fig. 3. PIRT methodology flow chart.
    'This ranking depends strongly on the amount of core uncovered during this phase as well as the duration of core uncovering during this phase. PIRT for fuel rods. Table 1
    *This is the most important (in terms of affecting the PCT) to understand phenomenon in a SBLOCA. 31 forced depressurization of the Secondary Side occurs after this phase, then the phenomenon — L. If forced depressurization of the Secondary Side occurs during or before this phase, then the phenomenon — H. Also, if the distribution of the reflux condensation water is even then the phenomenon - L. If the distribution of the reflux condensation water is uneven then the phenomenon — H. PIRT for reactor core. Table 2
    PIRT for upper head.
    PIRT for upper plenum.
    PIRT for hot leg. Table 5
    PIRT for pressurizer and surge pipe.
    PIRT for steam generator. Table 7
    PIRT for cross-over piping. Table 8
    PIRT for the accumulator tank. Table 11 Table 10
    PIRT for reactor coolant pumps. Table 9
    PIRT for the cold leg.
    PIRT for safety injection.
    PIRT for the downcomer and lower plenum.
    PIRT for break. Table 14
    PIRT for primary loop. Table 15 3.15. Primary loop
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    Analytical investigation of the draining system for a molten salt fast reactor
    by Shisheng Wang

    2024

    Molten Salt Fast Reactor (MSFR) is a conceptual design by European Union that contains a draining tank located underneath the reactor. In case of a planned reactor shut down or in emergency situations or in case of accidents leading to an... more
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    Safeometrics. About quantitative assessment of data for safety level determining
    by Dmitry J . Lobach

    2023, Promyšlennaâ bezopasnostʹ, ISSN 2958-4523

    Article is about development of methods for safety analysis and assessment. The accent made on the quantitative approach of analysis. There is discussed the subjects of the science about safety – safeology. There is proposed to use... more
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    Advanced numerical simulation and modelling for reactor safety − contributions from the CORTEX, HPMC, McSAFE and NURESAFE projects
    by Christophe Demaziere

    2023, EPJ Nuclear Sciences &amp; Technologies

    Predictive modelling capabilities have long represented one of the pillars of reactor safety. In this paper, an account of some projects funded by the European Commission within the seventh Framework Program (HPMC and NURESAFE projects)... more
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    Application of ATHLET/DYN3D/CTF to BWR TT without SCRAM
    by Yann Perin

    2023

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    Coupling of CTR with ATHLET and DYN3D on the SALOME platform
    by Yann Perin

    2023

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    CTF/DYN3D multi-scale coupled simulation of a rod ejection transient on the NURESIM platform
    by Yann Perin

    2023, Nuclear Engineering and Technology

    In the framework of the EU founded NURESAFE project the subchannel code CTF and the neutronics code DYN3D were integrated and coupled on the Salomé platform. The developments achieved during this three-year project include assembly level... more
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    Ein Berechnungsverfahren zur Behandlung von Profilströmungen mit lokalen Ablösezonen und offenen Totwassergebieten
    by Jochen Marzi

    2023

    BogenlangenkoordinateProfilnormaleSehnenkoordinateNormale zu:rProfiltiefedimensionslose Bogenlangenkoordinatedimensionslose ProfilnormaleVerdrangungsdickeImpulsverlustdickeFormparameterVVandschubspannungGrenzschichtdickeHohe... more
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    High-fidelity coupled Monte Carlo neutron transport and thermal-hydraulic simulations using Serpent 2/SUBCHANFLOW
    by victor hugo espinoza

    2023, Annals of Nuclear Energy

    Efforts to develop high-fidelity, in silico or ab initio, high performance multi-physics tools are undertaken by many groups due to the availability of relatively cheap, large-scale parallel computers. To this end, an internal coupling... more
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    A Serpent2-SUBCHANFLOW-TRANSURANUS coupling for pin-by-pin depletion calculations in Light Water Reactors
    by Luigi Mercatali

    2023, Annals of Nuclear Energy

    This work presents the development of a coupling scheme for Serpent2, a continuous-energy Monte Carlo particle transport code, SUBCHANFLOW, a subchannel thermalhydraulics code, and TRANSURANUS, a fuel-performance code, suitable for... more
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    Berechnung des Notkondensators des Integralreaktors CAREM
    by denis walter

    2023

    CAREM is an Argentine project to achieve the development, design and construction of an innovative, simple and small Nuclear Power Plant (NPP). This NPP has an indirect cycle reactor with some distinctive and characteristic features (e.g.... more
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    Analytical Modeling of the Emergency Draining Tank for a Molten Salt Reactor
    by Shisheng Wang

    2022

    The Molten Salt Fast Reactor is a reactor concept developed by the European Union based on a liquid fuel salt circulating through the reactor core. A peculiar emergency system, which takes advantage of the liquid fuel state, is... more
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    Advanced multi-physics simulation for reactor safety in the framework of the NURESAFE project
    by Victor Hugo Sanchez Espinoza

    2022, Annals of Nuclear Energy

    Since some years, there is a worldwide trend to move towards ''higher-fidelity'' simulation techniques in reactor analysis. One of the main objectives of the research in this area is to enhance the prediction capability of the... more
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    Legal and Regulatory Development of Nuclear Energy in Bangladesh
    by Ridoan Karim

    2022, Energies

    The adequacy of legal and regulatory framework relating to nuclear energy in Bangladesh has sparked many questions since the government took the formal decision to establish a nuclear power plant (NPP) at Rooppur. Consequently, the... more
    Figure 1. Worldwide nuclear energy production via number of reactors and overall capacity. Adapted from [12].
    Figure 2. Heat map of worldwide nuclear power generation in nominal terms and as percentage of overall domestic power generation. Adapted from [12].
    Figure 3. Worldwide energy source distribution (Total of 24,345 TWh). Adapted from [12].
    Figure 4. Hierarchy of the Laws in Bangladesh. = Moreover, it is additionally required to proceed with the issue with cautious and sincere insight or the improvement of the country and its long-term sustainable growth. From an economic point of riew, considering the scarcity of resources, we should make present day energy authorities accessible n view of equality and non-segregation to the entire populace including those who are left behind by he society; the most underprivileged.
    Figure 5. Structure and hierarchy of Bangladesh government related to nuclear affairs.
    Figure 6. Functions of Bangladesh Atomic Energy Regulatory Authority. There is additionally an arrangement in the BAER Act (2012) that permits the NSRC rules (1997) made under the canceled NSRC Act (1993) keep on being operational as though it were enacted currently, whereby the Act is presumed to enforce thorough and definite directions set up under the BAER Act (2012). These principles (NSRC Rules 1997) likewise give rundown of pertinent standard, code and support mechanisms important to various phases of nuclear establishments to guarantee atomic safety and security.
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    Analytical Modeling of the Emergency Draining Tank for a Molten Salt Reactor
    by Shisheng Wang

    2022

    The Molten Salt Fast Reactor is a reactor concept developed by the European Union based on a liquid fuel salt circulating through the reactor core. A peculiar emergency system, which takes advantage of the liquid fuel state, is... more
    Fig. 1. EDT cooling assembly scheme and model unit cell
    Fig. 2. Eigenvalue search for a slab case. In order to comply with the limit, we consider reducing the inert salt thickness, which hinders
    One can see in Fig. 4 that the temperature trend of the different options start to diverge af- ter a couple of hours, i.e. when the thermal ca- pacity of the 7 cm inert salt layer approaches saturation; in a temperature profile, like Fig. 5, a measure of the remaining available heat ca- pacity is given by the curvature of the profile (its second derivative): for a non-heat-generat- ing material, a positive curvature indicates that some energy can still be stored, while a nega- tive one denotes an excess of energy stored, e.g. due to the reduction of the temperature of the heated side. pacity is given by the curvature of the profile
    Fig. 5. Temperature profile (cylinder) of the 14/50 mm EDT element between 0 and 24 h, with intervals of 30 minutes (lines color is darker as time progresses). Grace time
    Fig. 6. Fuel maximum temperature (solid lines) and inert salt minimum temperature (dotted line) along the transient.
    The assessment of the solidification behavior of the frozen salt represents an important mat- ter for the EDT design. In the draining phase, a quick solidification should be avoided, as it could block the gaps and create an obstacle to a uniform and complete discharge. In addition, the fuel salt liquid state is required to ensure reversibility of the draining operation. Fig. 7. Available fuel gap for salt flow in the first minutes after draining.
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    Natural Convection Heat Transfer in Two-Fluid Stratified Pools with Internal Heat Sources
    by Askar GUBAIDULLIN

    2022

    Natural convection is a subject of interest in fundamental fluid dynamics and heat transfer, as well as in a great number of engineering applications. In particular, knowledge of thermal convection driven by internal heat sources is of... more
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    Environmentally benign and novel management route for radioactive corrosion products by hydroxyapatite
    by Muhmood ul Hassan

    2022, Journal of Nuclear Materials

    The direct solidification of the captured corrosion products by HA has been investigated. No organic binders were used for solidification of M-HA matrix. The sintered matrix showed good densification and mechanical properties. ASTM PCT... more
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    Adsorption and immobilization of radioactive ionic-corrosion-products using magnetic hydroxyapatite and cold-sintering for nuclear waste management applications
    by Muhmood ul Hassan

    2022, Journal of Nuclear Materials

    We have successfully demonstrated a new method of radioactive waste immobilization by hosting a wastebearing form in another waste matrix. A cold sintering route was used to consolidate a silica-incorporated hydroxyapatite (Si-HAp)... more
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    Nanocomposites for Decontamination of Multicomponent Technogenic Dilutions
    by Volodymyr Krasnoholovets

    2022, Journal of Nuclear Physics, Material Sciences, Radiation and Applications

    Employing model solutions we have tested a new technological method of neutralization of multi-metal containing effluences including low radioactive ones. The proposed approach seamlessly combines the positive properties of both physical... more
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    Polyaniline/akaganeite superparamagnetic nanocomposite for cadmium uptake from polluted water
    by Hesham Ibrahim

    2022, DESALINATION AND WATER TREATMENT

    The uptake of low concentration toxic cadmium ions from polluted water by polyaniline/akaganéite superparamagnetic nanocomposite was investigated. Akaganéite superparamagnetic nanoparticles (NPs) and polyaniline (PANI) doped with... more
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    Gd-DTPA Adsorption on Chitosan/Magnetite Nanocomposites
    by Dorota Kołodyńska

    2022, Nanoscale Research Letters

    The synthesis of the chitosan/magnetite nanocomposites is presented. Composites were prepared by co-precipitation of iron(II) and iron(III) salts by aqueous ammonia in the 0.1 % chitosan solution. It was shown that magnetite synthesis in... more
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    Testing FLUKA on neutron activation of Si and Ge at nuclear research reactor using gamma spectroscopy
    by ruben bruna

    2022, Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment

    Samples of two characteristic semiconductor sensor materials, silicon and germanium, have been irradiated with neutrons produced at the RP-10 Nuclear Research Reactor at 4.5 MW. Their radionuclides photon spectra have been measured with... more
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    Removal of Lead Ions from Industrial Wastewater Using Magnetite Loaded On Silica Support
    by ahmed osama

    2022, Egyptian Journal of Chemistry

    A SERIES of magnetite supported silica (Fe 3 O 4 /SiO 2) nanoparticles with different Fe 3 O 4 loadings was prepared by co-precipitation method. Structural characteristics of the prepared adsorbents were investigated by X-ray diffraction... more
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    Polyaniline/akaganeite superparamagnetic nanocomposite for cadmium uptake from polluted water
    by Ayman El Tahan

    2022, DESALINATION AND WATER TREATMENT

    The uptake of low concentration toxic cadmium ions from polluted water by polyaniline/akaganéite superparamagnetic nanocomposite was investigated. Akaganéite superparamagnetic nanoparticles (NPs) and polyaniline (PANI) doped with... more
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    Testing FLUKA on neutron activation of Si and Ge at nuclear research reactor using gamma spectroscopy
    by ruben bruna

    2022, Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment

    Samples of two characteristic semiconductor sensor materials, silicon and germanium, have been irradiated with neutrons produced at the RP-10 Nuclear Research Reactor at 4.5 MW. Their radionuclides photon spectra have been measured with... more
    Figure 2: Theoretical neutron spectrum of RP-10 nuclear reactor at position Al normalized with experimental integrated fluxes obtained with the activated foil dosimetry ko parametric method [15]. This spectrum is used in the FLUKA simulation. Figure 2: Theoretical neutron spectrum of RP-10 nuclear reactor at position Al normalized
    Figure 1: Configuration scheme of RP-10’s 44 core. The codes are: TN (used irradiation position), A and NN (nuclear fuel element), AS and NC (control fuel element), BE(beryllium reflector), GR (graphite), CI (irradiation box), BCF (fine control bar) and CF (fission counter). Figure 1: Configuration scheme of RP-10’s 44 core. The codes are: TN (used irradiation ~10%. The theoretical neutron spectrum of a thermal reactor, shown in Fig.
    Figure 3: Efficiency of ORTEC model GEM70P4 spectrometer used at two different detection distances. The shadowed bands represent the estimated error. characteristics, not described in the simulation. wards in order to account for the gamma spectroscopic measurement specific
    Figure 4: Time evolution of spectrometer measurements with theoretical fitting for silicon products. The shadowed band represents the error of the fit. Points are drawn at the end of the measurement and include the decay time.
    Figure 5: Gamma spectrum of neutron activated samples comparing experimental measure- germanium samples, respectively. ments (IPEN Data)and FLUKA simulations for peaks with intensities greater than 1% and with the constant fit is estimated to be 0.84% and 0.17% for the silicon and
    Table 2: Samples irradiation and detection parameters. Measurements at different times for each sample and their corresponding dead times are given. Table 2: Samples irradiation and detection parameters. Measurements at different times for
    Table 3: Residual nuclei, by atomic number and mass number (A), estimated with FLUK£ Table 3: Residual nuclei, by atomic number and mass number (A), estimated with FLUKA for the silicon and germanium samples. Values have been normalized to the maximum of each sample.
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    Comparison between Ag (I) and Ni (II) removal from synthetic nuclear power plant coolant water by iron oxide nanoparticles
    by mohsen askarishahi

    2022, Journal of Environmental Health Science and Engineering

    The impact of effective parameters such as iron oxide nanoparticles dosage, contact time and solution pH was optimized for removal of Ag(I) and Ni(II) in the nuclear cooling system and the best conditions were compared. Nearly complete... more
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    Atomic Absorption and Vibrational Spectral Magnetic Studies on the Removal of Cu(II) and Co(II) Ions Using Synthetic Nano Adsorbent Fe&lt;sub&gt;3&lt;/sub&gt;O&lt;sub&gt;4&lt;/sub&gt
    by kottai samy

    2021, Soft Nanoscience Letters

    Adsorption of Cu(II) and Co(II) from aqueous solutions on synthetic nano Fe 3 O 4 has been studied. The effect of experimental parameters such as initial concentration of the metal ions, adsorbent dosage, contact time and pH has been... more
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    Removal of lead (II) ions from aqueous solution by Hydroxyapatite biosorbent extracted from Ostrich bone
    by Associate Professor Dr. komal P R A S A D Malla

    2021

    Hydroxyapatite (HAp) is a broadly studied bioceramic for biomedical implant and bone tissue regeneration. Despite this, it is a good adsorbent of heavy metal ions. Its chemical formula is Ca10 (PO4)6(OH) 2. It was extracted by the... more
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    Magneto-separation of genomic deoxyribose nucleic acid using pH responsive Fe 3 O 4 @silica@chitosan nanoparticles in biological samples
    by vidya karande

    2021, RSC Adv.

    Magneto-separation of genomic deoxyribose nucleic acid using pH responsive Fe3O4@silica@chitosan nanoparticles in biological samples.
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    Lead ion removal from water by hydroxyapatite nanostructures synthesized from egg sells with microwave irradiation
    by Marzieh Torabbeigi

    2021, Applied Water Science

    Hydroxyapatite nanostructures were synthesized by microwave irradiation from egg shells. This nanoadsorbent was used for effective removal of lead ions from water and wastewater samples. The effects of experimental conditions such as pH,... more
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    The use of titanium (IV) phosphate for metal removal from aqueous and alcoholic samples
    by Devaney Ribeiro do Carmo

    2021, SN Applied Sciences

    Adsorption methods are widely employed for the removal of metals from aqueous medium, being an efficient and environmentally friendly technique for wastewater treatment. From the several adsorptive materials that are being employed by the... more
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    Predictive modeling and validation of arsenite removal by a one pot synthesized bioceramic buttressed manganese doped iron oxide nanoplatform
    by Satyakam Patnaik

    2021, RSC Adv.

    Arsenite removal by a one pot synthesized bioceramic buttressed manganese doped iron oxide nanoplatform.
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    Preparation and performance of a novel composite as a reactive resin for copper retention
    by Reda R . Sheha

    2021, Chemical Engineering Journal

    h i g h l i g h t s " Nickel hexacyanoferrate loaded on nanoscale iron ferrite was synthesized. " The nano-resins had homogeneous geometric shapes with 15-25 nm average size. " Copper removal was attained through participation of... more
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    New materials for removing nitrate, manganese and iron from groundwater
    by Cristina Orbeci

    2021, SIMI 2019, Abstract Book

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    BIOACTIVE NANOCOMPOSITES BASED ON POLYPYRROLE AND POLYANILINE AS A HIGHLY EFFICIENT ADSORBENTS IN REMOVAL OF Pb AND Cd, USEABLE IN HOUSEHOLD WATER TREATMENT
    by vahid Hasantabar

    2021, Journal of Materials Science and Engineering with Advanced Technology

    The development of simple methods for the removal of heavy metal cations from water samples is an attractive field of research. In this regard, two novel magnetic tri-layer core-shell-shell bioactive nanocomposites,... more
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    BIOACTIVE NANOCOMPOSITES BASED ON POLYPYRROLE AND POLYANILINE AS A HIGHLY EFFICIENT ADSORBENTS IN REMOVAL OF Pb AND Cd, USEABLE IN HOUSEHOLD WATER TREATMENT
    by vahid Hasantabar

    2021, Journal of Materials Science and Engineering with Advanced Technology

    The development of simple methods for the removal of heavy metal cations from water samples is an attractive field of research. In this regard, two novel magnetic tri-layer core-shell-shell bioactive nanocomposites,... more
    Scheme 1. Schematic explanation of the synthetic pathway and activity
    8(pH = 6, Co = 20ppm), (dosage = 10mg, Co = 20ppm), °(dosage = 10mg, pH = 6),
    “(pH = 6, Co = 20ppm), b(dosage = 10mg, Cp = 20ppm), “(dosage = 10mg, pH = 6), Table 3. Optimization of the adsorption parameters for Pb(II) sorption by 4 (dosage = 10mg, pH = 6, Cg = 20ppm). The bold numbers are optimum values.
    (pH = 6, Co = 20ppm), ‘(dosage = 10mg, Cp = 20ppm), “(dosage = 10mg, pH = 6). 4 (dosage = 10mg, pH = 6, Co = 20ppm). The bold numbers are optimum values. Table 4. Optimization of the adsorption parameters for Cd(II) sorptior
    According to the data from Table 5, it is comprehensible that the
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    Adsorption of Phosphate from Aqueous Solution onto Iron-coated Waste Mussel Shell: Physicochemical Characteristics, Kinetic, and Isotherm Studies
    by Nur Atikah Abdul Salim

    2021, Biointerface Research in Applied Chemistry

    High amounts of phosphate (PO 4 3-) discharged in receiving water can lead to eutrophication, which endangers life below water and human health. This study elucidates the removal of PO 4 3from synthetic solution by iron-coated waste... more
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    Legal and Regulatory Development of Nuclear Energy in Bangladesh
    by Ridoan Karim

    2020, Energies, Multidisciplinary Digital Publishing Institute

    The adequacy of legal and regulatory framework relating to nuclear energy in Bangladesh has sparked many questions since the government took the formal decision to establish a nuclear power plant (NPP) at Rooppur. Consequently, the... more
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    ADSORPTION OF LEAD IONS (PB2+) FROM AQUEOUS SOLUTION WITH TETRA-ETHYL ORTHOSILICATE MODIFIED SILICA-IRON OXIDE (SI-FE3O4) MAGNETIC NANO-ADSORBENT
    by Ogel Publications

    2020

    Lead as one of the toxic and dangerous heavy metals will always require an approach that is cost-effective, simple and environmentally benign to eliminate it from potable water sources especially. Tetra-ethyl orthosilicate was employed as... more
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    Preparation and characterization of novel mesoporous chitin blended MoO 3 -montmorillonite nanocomposite for Cu(II) and Pb (II) immobilization
    by Hany F A T H Y Heiba

    2020

    A novel mesoporous chitin blended MoO 3-Montmorillonite nanocomposite was prepared through three-steps synthesis. First, chitin was extracted from prawn shell then MoO 3-MMT was prepared, and lastly, chitin was blended with MoO 3-MMT.... more
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    ADSORPTION OF LEAD IONS (PB2+) FROM AQUEOUS SOLUTION WITH TETRA-ETHYL ORTHOSILICATE MODIFIED SILICA-IRON OXIDE (SI-FE3O4) MAGNETIC NANO-ADSORBENT
    by IJCIRAS Research Publication

    2020, IJCIRAS

    Lead as one of the toxic and dangerous heavy metals will always require an approach that is cost-effective, simple and environmentally benign to eliminate it from potable water sources especially. Tetra-ethyl orthosilicate was employed as... more
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    Safety Study and Human Factor Assessment of End- Shield Draining Event for 220MWe Indian PHWRs
    by krishnakumar P

    2019, ICRESH 2010

    In Indian PHWRs (Pressurized Heavy Water Reactors), one of the major functions of the end-shield cooling system is to maintain temperature across the end-shield components uniform and thereby minimizing thermal stresses. Safety analysis... more
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    EVALUATION OF REACTOR COMPONENTS TEMPERATURE DURING PROLONGED STATION BLACK OUT (SBO) FOR 540MWe PHWR
    by krishnakumar P

    2019, 24th National and 2nd International ISHMT-ASTFE Heat and Mass Transfer Conference (IHMTC-2017),

    TAPP-3&4 is a 2 x 540 MWe, Pressurized Heavy Water Reactor (PHWR) using heavy water moderator, heavy water coolant and natural uranium dioxide as fuel. A postulated situation involving failure of both Class-IV(off site) and Class-III (on... more
    Sources, Sinks
    FIGURE. 1: Schematic diagram of End shield & End fitting
    concentric calandria tube has been provided with an annular gap. Carbon dioxide gas filled in this gap serves as thermal insulation between the high temperature coolant in pressure tubes and low temperature moderator. The stainless steel reactor vessel (calandria) has integral end- shields at either end filled with carbon steel balls and water to limit radiation dose in Fuelling Machine (F/M) vaults. The re-circulating water removes the heat generated in the end shields and carries it to plate type heat exchangers where it is transferred to Active Process Water (APW). The schematic diagram of Calandria side tube sheet (CSTS), end fitting and end shield ball and water mixture are shown in Figure -1.
    FIGURE 3:End shield lattice model (Description of modelled heat transfer paths from end fittings to lattice The components and fluids are connected with each other by considering the resistance between them. The resistances are calculated by conduction, convection and radiation. A simplified end fitting, end shield and ball water portion is shown in Figure-3. The simplified resistance diagram, which connects all the fluids and components are shown in Fig-4.
    FIGURE 4: Thermal resistance diagram of fluids/components
    TABLE 3: TEMPERATURES OF THE COMPONENTS WHEN PRIMARY HEAT TRANSPORT SYSTEM WHEN CRASHCOOLDOWN IS INITIATED
    FIGURE 5: Primary Heat Transport Temperature Variation Nuclear Heat generation for 100%FP operation TABLE 2: Primary heat transport system temperature variation is used as the boundary condition for the reactor component
    FIGURE 6. Temperature Profiles of Moderator , Calandria vault water and end shield water The analysis is extended for 7 days. The moderator, end shield water and calandria vault water temperature for 7 days of station black out are shown in Figure-6. The core and end shield component temperatures are shown in Figure-7.
    From the results, it is found that the cooling fluid except calandria vault water are less than their saturation temperature. Reactor component temperature and _ rolled joint temperatures are less than their design temperature. Calandria vault water temperature exceeds its saturation temperature around 1.8 days and around 55 tons of its inventory evaporates upto 7 days (Still the water level in the calandria vault is much above the Calandria top). Furthermore hookup provision exits to makeup the calandria vault inventories. The calandria vault water inventory and its temperature are shown in figure-8. FIGURE 8. Calandria Vault Water Inventory and Temperature Variations.
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    Plackett-Burman experimental design for the removal of diazinon pesticide from aqueous system by magnetic bentonite nanocomposites
    by Journal of Applied Research In Water and Wastewater

    2019

    The present study demonstrates the effective removal of diazinon pesticide from aqueous solutions by means of magnetic bentonite nanocomposite. The product was characterized by advanced techniques like scanning electron microscope (SEM),... more
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    Enhanced adsorption of dyes on microwave-assisted synthesized magnetic zeolite-hydroxyapatite nanocomposite
    by afsaneh mollahosseini

    2019

    In the present study, magnetic zeolite/hydroxyapatite (MZeo-HAP) nanocomposite was successfully synthesized using microwave-assisted method for the removal of Reactive Orange 5 (RO5), Reactive orange 16 (RO16), and Congo red (CR) anionic... more
    Cilinoptilolite natural zeolite (about 6g) was firstly washed with DI water and dried in oven. Secondly, it was dispersed in tetramethyl ammonium chloride solution (250 mL, 0.40 mol/L) and ultrasonicated for 30 min to obtain an aqueous dispersion zeolite. Then two iron electrodes with 1cm x 1cm (anode) and 1cm x 4cm (cathode) di- mension and 0.20 mm thick were placed inside the solution and the distance between them was adjusted to 1 cm. The oxidation potential of 8 V was applied to the electrodes by a potentiostat / galvanostat and the reaction was carried out under ultrasonic irradiation at 90°C for 1h. Finally, an external magnetic field was used to separate MZeo. Finally, obtained MZeo was repeatedly washed with DI water and methanol and dried at 65°C.
    Fig. 3. (a, b) SEM image, (c) EDAX of MZeo-HAP, (d, e) TEM images of MZeo-HAP. The functional group peaks of the compounds are observed in the figure. The bands observed at wavenumbers of 440 and 610cm 7! are ascribed to the Fe-O bonds in Fe304 MNPs (Fig. 4a) [32]. The Fig. 4b represents the MZeo FTIR spectrum. The band placed at 1100 cm™' is attributed to asymmetric stretching vibration of the Al-O-Si in the zeolite structure. Also, Al (Si)-O bending mode was observed with at 464 cm". To verify the presence of magnetic nanoparticles in the syn- thesized MZeo, the sharp band observed at 608 cm™ was due to the Fe- O bond. After modification of the MZeo by HAP, new bands were de- tected (Fig. 4c). In this spectrum, the bands at 567, 603, and 1032 cm-" clearly showed the formation of O—P—O bonds in the synthesized na- nocomposite which were related to the presence of the HAP in the adsorbent [33]. It is noteworthy saying that magnetic particles and zeolite could also be detected in the FTIR pattern of MZeo-HAP. XRD pattern of MZeo-HAP nanocomposite ranging (26) from 5 ° to 60 ° is depicted in Fig. 4d having numerous detectable peaks. All the peaks of synthesized nanocomposite are consistent with database of HAP (JCPDS No. 09-0432), clinoptilolite (JCPDS No. 39-1383) and Fe30, (JCPDS No. 19-0629) in the JCPDS-International Center for Diffraction Data file. According to the figure, diffraction peaks at 35.43
    Fig. 2. Synthesis scheme for MZeo-HAP nanocomposite preparation.
    Fig. 4. (a, b, c) FTIR of Fe304,, MZeo, and MZeo-HAP, (e) XRD and (d) VSM of MZeo-HAP.
    Fig. 5. Nz adsorption-desorption isotherms for MZeo-HAP.
    Fig. 6. Schematic illustration for CR adsorption by MZeo-HAP via electrostatic attraction at low pH.
    Fig. 7. The effect of (a) pH, (b) pHzp- of MZeo-HAP, (c) contact time, (d) adsorbent dosage, (e) dye concentration and (f) temperature on adsorption efficiency
    3.12. Method validation Fig. 8. The comparison of MZeo and MZeo-HAP in terms of dye removal.
    Textual property of zeolite, MZeo, and MZeo-HAP nanocomposite. Table 1
    Thermodynamics parameters calculated for the examined dyes. Table 2 endothermic, which favors the greater adsorption capacity at higher temperatures [46].
    Obtained parameters from studied isotherm models.
    Obtained parameters from PFO, PSO, and Elovich kinetics models.
    Comparison of adsorption capacities of different adsorbents toward dye removal. Table 5
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    Environmentally benign and novel management route for radioactive corrosion products by hydroxyapatite
    by Muhmood ul Hassan

    2018, Journal of Nuclear Materials

    A novel and environmentally benign route for the direct solidification of captured corrosion products (Co, Cr, Fe, Ni, Cu, Zn, and Mn) generated from the primary coolant system of nuclear power plants is introduced in this study.... more
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    Adsorption and immobilization of radioactive ionic-corrosion- products using magnetic hydroxyapatite and cold-sintering for nuclear waste management applications
    by Muhmood ul Hassan

    2018, Journal of Nuclear Materials

    A simple and efficient method for the adsorption and immobilization of the radioactive ionic-corrosion-products Co 2þ , Cr 3þ , Mn 2þ , Fe 2þ , Ni 2þ , Cu 2þ and Zn 2þ generated in nuclear reactor coolant has been developed using a... more
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