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Reactor Safety

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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.
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.

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
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
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

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.

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
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
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
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
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
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

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.

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

All papers in Reactor Safety

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
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
Several adhesive tapes have been studied in terms of their suitability for securing gold wires into positions for neutron flux measurements in the reactor core and irradiation facilities surrounding the core of the Open Pool Australian... more
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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