Discover published sets by community

Deterministic Risk Assessment uses predefined scenarios to assess risks and the adequacy of safety systems. Nuclear facilities use it to ensure that safety systems can withstand design basis accidents like equipment failure or natural disasters.

Risk Communication is the process of exchanging information about risk levels and safety among stakeholders. Effective communication is crucial in the nuclear industry to build public trust and to inform decision-making during emergencies.

Residual Risk is the risk that remains after all safety measures have been applied. Nuclear risk management seeks to minimize this risk to a level that is as low as reasonably practicable (ALARP) through continuous improvements in safety.

Defense in Depth is a safety philosophy that employs multiple layers of protection to prevent accidents or to mitigate consequences. Nuclear power plants utilize redundant and diverse systems to ensure safety even if one layer fails.

Severe Accident Analysis evaluates the consequences of rare but catastrophic events in nuclear power plants. It's used to understand the potential for core melt, containment failure, and widespread radiological release, and to enhance safety measures.

Safety Culture is the set of shared beliefs, norms, attitudes, roles, and practices concerning safety within an organization. Nuclear facilities emphasize a strong safety culture to ensure that safety is prioritized at all levels and in all operations.

Incremental Risk measures the additional risk from extending the life of a nuclear power plant or making modifications. Safety reviews of incremental risks ensure that safety standards are not compromised over time or through changes.

QHOs represent defined levels of risk that are considered acceptable. In the nuclear industry, they guide the design and operation of facilities to maintain public and worker health risks from radiation within acceptable limits.

The NRC Regulatory Guide contains principles and methods for nuclear facility design and operation to ensure safety. Operators refer to this guide to comply with federal regulations and to maintain permission to operate.

Stochastic Modeling uses probability and random variables to represent systems that are inherently uncertain. This method is applied in nuclear facilities to model the unpredictable behavior of systems for risk assessment and safety analysis.

LERs are reports submitted by nuclear facility operators to the regulatory body following certain predefined events. These reports help in understanding operational weaknesses and in improving the overall safety protocol.

Reliability Engineering ensures that components and systems function as intended in a safe and consistent manner. In nuclear facilities, it is crucial for the design and maintenance of systems to prevent accidents and to comply with safety regulations.

HRA assesses the likelihood of human error and its impact on system safety and performance. In the nuclear industry, it's applied to evaluate the potential for operator error and to develop strategies to reduce these risks.

Technical Specifications outline the operational limits and conditions necessary to ensure the safety of a nuclear facility. These are legally binding parameters and are used to control plant operations within safety margins.

PRA, or Probabilistic Safety Assessment (PSA), quantitatively evaluates the risk of hazardous events. It's used in nuclear power plants to assess the likelihood of core damage, the effectiveness of safety systems, and potential release of radioactive materials.

FTA is a top-down approach to identify the root causes of system failures. In nuclear facilities, it's used to analyze potential failure paths in safety systems and to prioritize corrective actions.

Redundancy refers to the duplication of critical components or functions in a system to increase reliability. In nuclear facilities, redundancy is built into safety systems to ensure that if one path fails, another can perform the required function.

Common Cause Failure involves the simultaneous failure of multiple components due to a shared cause. Nuclear power plants analyze such failures to prevent situations where multiple safety systems might fail at once.

A Safety Case is a comprehensive set of documents that proves a nuclear facility can be operated safely. It includes safety assessments, operational limits and conditions, and an outline of the safety management system.

Spent Fuel Pool is used for temporary storage of spent nuclear fuel under water. Risk assessments must ensure the structural integrity and cooling capability to prevent overheating and potential release of radioactive materials.

PGA is a measure of earthquake acceleration that is applied to the soil at a location. Nuclear plants must be designed to withstand the PGA from the strongest expected earthquake in their region to prevent catastrophic failure.

Single Point of Failure is a component or system whose failure can lead to the failure of the entire operation. In nuclear facilities, engineers work to identify and eliminate these vulnerabilities to enhance overall safety and reliability.

Safety Margin is the extent to which a system or component operates within its design capacity. In nuclear engineering, maintaining ample safety margins ensures that operations stay within safe limits even during transients or accidents.

LOCA is a scenario where the coolant is lost from the reactor's cooling system, potentially leading to overheating and core damage. Nuclear plants are designed with multiple safety systems to address this risk and protect against core meltdown.

ETA is a forward-looking analysis technique to investigate the possible outcomes following an initiating event. It's used in nuclear engineering to predict the progression of potential accident scenarios and their consequences.

ALARP involves reducing risks to a level that is as low as reasonably practicable by weighing the risk against the trouble, time, and cost of taking measures to reduce it. In nuclear facilities, it's applied to ensure radiation exposure of workers and the public is minimized given economic and social factors.

Seismic Hazard Analysis assesses the probability of various levels of seismic events at a site. For nuclear facilities, this analysis is crucial to ensure that structures, systems, and components are designed to withstand seismic events.

The Safety Injection System is used to automatically provide a coolant to the reactor core during a loss of coolant accident (LOCA). The system's reliability is critical for preventing core damage and limiting risk in nuclear power plants.

The Containment Building is a robust structure surrounding the reactor to prevent the escape of radioactive materials. Its integrity is vital for nuclear plant safety, particularly in the event of severe accidents or external events like explosions or fires.

The EPZ is a defined area around a nuclear power plant where emergency measures are planned and implemented to protect public health and safety in case of a nuclear accident. Its size and shape depend on plant-specific conditions.

SBO refers to the loss of all off-site power to a nuclear power plant, along with failure of emergency power sources. Risk assessments for SBO events focus on maintaining cooling and safety functions to prevent core damage.

DBT defines the threat against which the physical protection of the plant must be designed to defend. It includes a spectrum of adversarial actions, such as sabotage or theft of nuclear material, that a nuclear facility might face.

Internal Event Assessment evaluates the risks associated with events originating within the plant, such as equipment failure or human error. The assessments help nuclear facilities to enhance safety systems and procedures.

A Risk Matrix is a tool used to define and prioritize risks by assigning a risk rating based on the likelihood and impact of an event. Nuclear regulatory bodies may use a Risk Matrix to categorize and manage safety risks associated with nuclear operations.