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Refers to the combination of group values and behaviors that prioritize safety over production or financial goals in a nuclear facility.

An automatic rapid shutdown of a nuclear reactor in response to certain predetermined conditions that indicate a possible safety violation or malfunction.

The processes involved in handling, treating, and disposing of waste that has been contaminated by or contains radioactive substances to protect human health and the environment.

A nuclear plant design principle which states that the failure of a single component should not lead to a loss of safety function in a system.

The process of retiring a nuclear facility in a manner that ensures the safety of the public and environment by removing radioactive contaminants and reducing residual radioactivity to a level permitting release for unrestricted use.

A method of storing spent nuclear fuel in which the fuel is encased in airtight steel or concrete containers and stored above ground.

QA entails the systematic procedures, standards, and activities designed to ensure that nuclear facility components and systems perform to pre-determined quality standards.

The science and practice of protecting people and the environment from harmful effects of ionizing radiation.

A phenomenon in nuclear reactors where the reactor vessel is rapidly cooled, causing thermal stresses that might compromise the integrity of the vessel if not properly managed.

An emergency shutdown of a nuclear reactor – the rapid insertion or fall of control rods into the reactor to stop the nuclear reaction.

The composition and quantity of radioactive materials released or potentially released from a nuclear plant during an accident, used in accident analysis and emergency response planning.

In reactor safety, TOF refers to the measurement of neutrons' speed through the reactor, which is critical for understanding neutron behavior and maintaining control of the reactor.

A principle and set of actions that aim to prevent the spread of nuclear weapons and weapon technology, ensuring that nuclear technology is used solely for peaceful purposes.

The component that houses the nuclear fuel and where the fission reaction takes place. Its integrity is crucial as it is subjected to the extreme conditions inside the reactor.

Technologies, policies, and procedures implemented to ensure the safe operation of a nuclear reactor, and deal with potential accidents or to mitigate their consequences.

Structures or materials in a reactor designed to prevent the release of fission products in the event of leakage or accident, maintaining containment.

The outer layer of the fuel rods in a nuclear reactor, made of a corrosion-resistant material that prevents the release of fission products during normal operation and accidents.

A condition where a nuclear reaction is self-sustaining. Criticality control ensures that the nuclear chain reactions are kept under control and do not lead to an uncontrolled release of energy.

A physical construction within a nuclear reactor designed to reduce heat transfer, helping to maintain the structural integrity of the reactor and prevent overheating.

Systems and processes in nuclear reactors designed to remove heat left in the reactor core after the nuclear fission process has been shut down.

A comprehensive document that provides the analysis of potential accidents that could occur at a nuclear facility and describes how the facility is designed to prevent or mitigate these accidents.

The discipline of incorporating human psychology and physiology in the design and operation of nuclear facilities to reduce the risk of human error and enhance safety and performance.

Designing nuclear systems in such a way that the physical and chemical characteristics inherently eliminate or significantly reduce the possibility of accidents.

In nuclear safety, containment refers to methods or structures used to prevent the release of radioactive substances during normal operation or in the event of an accident.

A probabilistic risk assessment term that indicates the likelihood of a reactor core experiencing severe damage per year of operation.

A system designed to ensure the integrity of critical safety functions and typically used to mitigate risks of catastrophic events in nuclear facilities.

An independent agency of the United States government tasked with regulating commercial nuclear power plants and other uses of nuclear materials.

A measure of nuclear fuel utilization, quantified by the energy produced per unit mass of fuel, influencing both the economic aspects and the formation of high-level waste.

A safety philosophy used in nuclear engineering that employs multiple layers of redundancy in design, operation, and management to ensure safety even if one component fails.

An accident at a nuclear power plant that leads to significant core damage with the potential release of large quantities of radiation into the environment.

This principle involves having multiple identical components performing the same function so that if one fails, the other can take over without any loss of functionality.

A model used in radiation protection to quantify the health effects of low levels of ionizing radiation, proposing that the health risk is directly proportional to the dose, with no threshold.

The process of injecting coolant into a reactor core during an emergency to ensure the core is kept cool and to help maintain the plant in a safe state.

A comprehensive evaluation of a nuclear facility that examines all aspects of plant design, operation, and maintenance to assess the overall safety conditions.

These are requirements, or limits set for operational parameters to ensure safe operation of a nuclear reactor.

A pool of water used for the storage of spent nuclear fuel from a reactor. It cools the fuel and provides shielding from radiation.

The procedures and measures taken after a nuclear accident to stabilize the situation, ensure safety, and prepare for long-term recovery.

ALARA stands for 'As Low As Reasonably Achievable.' It's a safety principle aimed at minimizing radiation doses and releases of radioactive materials by employing all reasonable methods.

The difference between the actual condition of something (like the output of a reactor) and its maximum limit or the condition at which failure occurs.

The ECCS is a set of systems in nuclear reactors that are specifically designed to safely shut down a reactor and maintain it in a safe condition during and after an accident.