REGDOC-3.6, Glossary of CNSC Terminology - Glossary - C

With respect to CANDU nuclear power plants, a cylindrical tank that houses the reactor’s fuel channels as well as the moderator. See also calandria tube.

With respect to CANDU nuclear power plants, one of a set of tubes that span the calandria and separate the pressure tubes from the moderator. Each calandria tube contains one pressure tube, with an insulating gas between the calandria tube and the pressure tube. See also calandria.

The calculational procedures – mathematical equations, approximations, assumptions, associated numerical parameters (such as cross-sections) – that yield the calculated results.

A period of 12 consecutive months beginning on January 1.

The process to verify that, with a known precision input, a model, instrument or channel parameter gives the required output.

See IAEA Agreement or safeguards agreement.

Canada’s nuclear regulator, established under the Nuclear Safety and Control Act to regulate the use of nuclear energy and materials to protect health, safety, security and the environment; to implement Canada’s international commitments on the peaceful use of nuclear energy; and to disseminate objective scientific, technical and regulatory information to the public.

See CSA Group.

A Canadian-invented pressurized heavy-water reactor that uses heavy water (deuterium oxide) for moderator and coolant and natural uranium for fuel. “CANDU” is short for CANada Deuterium Uranium. Also called CANDU.

Has the same meaning as in section 1.4 of the Transportation of Dangerous Goods Regulations. (Source:  Packaging and Transport of Nuclear Substances Regulations, 2015 )

criticality accident sequence assessment

See end-use controls.

A nuclear substance listed in column 1 of Schedule 1 that is in the corresponding form set out in column 2 and the corresponding quantity set out in column 3 of Schedule 1. (Source: Nuclear Security Regulations )

Note: Use Roman numerals for this term. Also note that categories for nuclear material do not have the same meaning as categories for sources (compare to Category 1 source).

A sealed source that, if not safely managed or securely protected, would be likely to cause permanent injury to a person who handled it, or was otherwise in contact with it, for more than a few minutes. It would probably be fatal to be close to this amount of unshielded radioactive material for a period of a few minutes to an hour. In Canada, these sources are typically used in practices such as self-shielded irradiators and radiation teletherapy. Note: Use Arabic numerals for this term. Also note that categories for sources do not have the same meaning as categories for nuclear material (compare to Category I nuclear material).

A nuclear substance listed in column 1 of Schedule 1 that is in the corresponding form set out in column 2 and the corresponding quantity set out in column 4 of Schedule 1. (Source: Nuclear Security Regulations )

Note: Use Roman numerals for this term. Also note that categories for nuclear material do not have the same meaning as categories for sources (compare to Category 2 source).

A sealed source that, if not safely managed or securely protected, could cause permanent injury to a person who handled it, or was otherwise in contact with it, for a short time (minutes to hours). It could possibly be fatal to be close to this amount of unshielded radioactive material for a period of hours to days. In Canada, these sources are typically used in practices such as industrial gamma radiography and oil well logging. Note: Use Arabic numerals for this term. Also note that categories for sources do not have the same meaning as categories for nuclear material (compare to Category II nuclear material).

A nuclear substance listed in column 1 of Schedule 1 that is in the corresponding form set out in column 2 and the corresponding quantity set out in column 5 of Schedule 1. (Source: Nuclear Security Regulations )

Note: Use Roman numerals for this term. Also note that categories for nuclear material do not have the same meaning as categories for sources (compare to Category 3 source).

A sealed source that, if not safely managed or securely protected, could cause permanent injury to a person who handled it, or was otherwise in contact with it, for some hours. It could possibly – although it is unlikely – be fatal to be close to this amount of unshielded radioactive material for a period of days to weeks. In Canada, these sources are typically used in practices such as fixed nuclear gauges and high dose rate brachytherapy. Note: Use Arabic numerals for this term. Also note that categories for sources do not have the same meaning as categories for nuclear material (compare to Category III nuclear material).

A sealed source that is very unlikely to permanently injure anyone. However, this amount of unshielded radioactive material, if not safely managed or securely protected, could possibly – although it is unlikely – temporarily injure someone who handled it or was otherwise in contact with it, or who was close to it for a period of many weeks. In Canada, these sources are typically used in practices such as portable nuclear gauges. Note: Use Arabic numerals for this term. Also note that categories for sources do not have the same meaning as categories for nuclear material (compare to Category I nuclear material, Category II nuclear material and Category III nuclear material).

A sealed source that could not permanently injure someone. In Canada, these sources are typically used in practices such as low dose rate brachytherapy or in gas chromatography instruments. Note: Use Arabic numerals for this term. Also note that categories for sources do not have the same meaning as categories for nuclear material (compare to Category I nuclear material, Category II nuclear material, and Category III nuclear material).

A change in one of the three categories of uranium: depleted uranium, natural uranium and enriched uranium. Category change results in the reduction of one category of uranium and a corresponding increase in another. Uranium can change category as a result of blending, enrichment, depletion or burnup. For example, natural uranium can become depleted uranium as a result of the burnup of uranium‑235.

See common-cause failure.

Canadian Council of Ministers of the Environment

Canadian Environmental Assessment Act, 2012

See certified exposure device operator.

Canadian Environmental Protection Act, 1999

Has the meaning in section 64 of the Canadian Environmental Protection Act, 1999 .

A document issued by the Commission or by a designated officer authorized under paragraph 37(2)(b) of the Act, indicating that a person is certified. (Source: Class I Nuclear Facilities Regulations )

OR

A document issued by the Commission or by a designated officer authorized under paragraph 37(2)(a) of the Act, indicating that a model of Class II prescribed equipment is certified, or authorized under paragraph 37(2)(b) of the Act, indicating that a person is certified. (Source: Class II Nuclear Facilities and Prescribed Equipment Regulations )

OR

A document issued by the Commission or by a designated officer authorized under paragraph 37(2)(a) or (b) of the Act, indicating that prescribed equipment or a person is certified. (Source: Nuclear Substances and Radiation Devices Regulations )

OR

A document issued by the Commission under paragraph 21(1)(h) of the Act or by a designated officer authorized under paragraph 37(2)(a) of the Act, indicating the certification of:

1. a package design;
2. a design for special form radioactive material;
3. a design for low dispersible radioactive material;
4. the calculation of a value demonstrating that fissile-excepted radioactive material will remain subcritical;
5. the calculation of the basic radionuclide value for radioactive material that has a basic radionuclide value that is not listed in the IAEA Regulations; or
6. the calculation, for an instrument or article that has an alternative activity limit for an exempt consignment, of the alternative activity limit.

(Source: Packaging and Transport of Nuclear Substances Regulations, 2015 )

A written attestation from the Commission, or from a designated officer authorized by it, that a person is qualified to carry out licensed activities (including the duties of a given position referred to in a licence).

Certified by the Commission under paragraph 21(1)(i) of the Act or by a designated officer authorized under paragraph 37(2)(b) of the Act. (Source: Class I Nuclear Facilities Regulations )

OR

Certified by the Commission under paragraph 21(1)(h) or (i) of the Act or by a designated officer authorized under paragraph 37(2)(a) or (b) of the Act. (Sources: Class II Nuclear Facilities and Prescribed Equipment Regulations ; Nuclear Substances and Radiation Devices Regulations ; Packaging and Transport of Nuclear Substances Regulations, 2015 )

A person who has the qualifications to safely operate industrial gamma radiography exposure devices anywhere in Canada and who is certified as such by the CNSC.

With respect to dosimetry information, any change to that information, such as a decrease or increase to an assigned dose value previously filed with the National Dose Registry. Normally, changes to dosimeter wearing periods are not included as a modification to dosimetry information.

critical heat flux

curie; see becquerel

A Class IA nuclear facility and a Class IB nuclear facility. (Source: Class I Nuclear Facilities Regulations )

Any of the following nuclear facilities:

1. a nuclear fission or fusion reactor or subcritical nuclear assembly; and
2. a vehicle that is equipped with a nuclear reactor.

(Source: Class I Nuclear Facilities Regulations )

Any of the following nuclear facilities:

1. a facility that includes a particle accelerator, other than a particle accelerator described in paragraphs (d) and (e) of the definition “Class II prescribed equipment” in section 1 of the Class II Nuclear Facilities and Prescribed Equipment Regulations ;
2. a plant for the processing, reprocessing or separation of an isotope of uranium, thorium or plutonium;
3. a plant for the manufacture of a product from uranium, thorium or plutonium;
4. a plant, other than a Class II nuclear facility as defined in section 1 of the Class II Nuclear Facilities and Prescribed Equipment Regulations, for the processing or use, in a quantity greater than 10¹⁵ Bq per calendar year, of nuclear substances other than uranium, thorium or plutonium;
5. a facility for the disposal of a nuclear substance generated at another nuclear facility; and
6. a facility prescribed by paragraph 19(a) or (b) of the General Nuclear Safety and Control Regulations.

(Source: Class I Nuclear Facilities Regulations )

A facility that includes Class II prescribed equipment. (Source: Class II Nuclear Facilities and Prescribed Equipment Regulations )

[Any of the following:]

1. an irradiator that uses more than 10¹⁵ Bq of a nuclear substance;
2. an irradiator that requires shielding which is not part of the irradiator and that is designed to deliver a dose of radiation at a rate exceeding 1 cGy/min at a distance of 1 m;
3. a radioactive source teletherapy machine;
4. a particle accelerator that is capable of producing nuclear energy and has a beam energy of less than 50 MeV for beams of particles with a mass equal to or less than 4 atomic mass units;
5. a particle accelerator that is capable of producing nuclear energy and has a beam energy of no more than 15 MeV per atomic mass for beams of particles with a mass greater than 4 atomic mass units; or
6. a brachytherapy remote afterloader.

(Source: Class II Nuclear Facilities and Prescribed Equipment Regulations )

Note: The abbreviation cGy/min means centigray per minute. MeV means megaelectron volts.

A document issued by the Commission or by a designed officer authorized under the Nuclear Safety and Control Act, indicating that a model of Class II prescribed equipment is certified for use.

Rock without the potential to release hazardous and/or nuclear substances that could have a significant adverse effect on human health or harm the environment. Clean rock may still require management for other reasons, such as to control erosion to prevent deposits of sand in local surface water bodies.

With respect to decommissioning, means the removal of contaminated soil from an area within the boundary of a facility, location or site.

With respect to radioactivity levels, the maximum permissible concentrations of radioactivity in or on materials, equipment and sites to be released from regulatory control (for example, becquerels per gram or per square centimetre, near-contact dose rates). Clearance levels may be expressed as conditional or unconditional, depending on whether the specific pathways of release, or destinations for reuse, recycling and/or disposal are specified.

A small change of conditions that may lead to a catastrophic increase in the severity of consequences. Note: Cliff-edge effects can be caused by changes in any of the following: environment characteristics, the event or the facility response.

See decommissioning.

See configuration management or corrective maintenance.

See Commission member document.

Convention on Nuclear Safety

See Canadian Nuclear Safety Commission.

Regulatory requirements and derived acceptance criteria that are related to nuclear criticality safety and listed in operating licence conditions or other legally enforceable documents.

Chapter 10 of the subsidiary arrangements of the Canada/IAEA Safeguards Agreement.

The degree of closeness of a calculated quantity to its actual value. Code accuracy comprises the bias and variability of bias of a computer code that are derived from the comparison of code predictions with experimental data.

See beam limiter.

A chemical process that involves oxidation sufficient to produce heat or light.

The Canadian Nuclear Safety Commission established by section 8. (Source: Nuclear Safety and Control Act)

Note 1: The Commission consists of not more than seven members, appointed by the Governor in Council, to:

• make independent, fair and transparent decisions on the licensing of nuclear-related activities
• establish legally binding regulations
• set regulatory policy direction on health, safety, security and environmental issues affecting the Canadian nuclear sector

Note 2: This term is not used when the intention is to refer to both Commission members and CNSC staff. See also Canadian Nuclear Safety Commission.

A document prepared for Commission hearings and meetings by CNSC staff, proponents and intervenors.

A term previously used to refer to the Commission. See Commission.

With respect to a reactor facility, a process intended to demonstrate that installed structures, systems and components (SSCs) perform in accordance with their specifications before the facility is placed in service or before the SSCs are returned or placed in service.

The plans, instructions, procedures, drawings, reviews, records, reports and the like, which together describe the commissioning of one or more structures, systems or components, or of the integrated reactor facility.

A report written on completion of commissioning activities to record results, assess compliance with the acceptance criteria, and record actions taken to rectify any deficiencies.

Pre-service testing to demonstrate that structures, systems and components perform within their design specifications.

In respect of a dose of radiation, received by an organ or tissue from a nuclear substance during the 50 years after the substance is taken into the body of a person 18 years old or older or during the period beginning at intake and ending at age 70, after it is taken into the body of a person less than 18 years old. (Sources: Radiation Protection Regulations ; Packaging and Transport of Nuclear Substances Regulations, 2015 )

See common-cause failure.

An event that leads to common-cause failures.

A failure of two or more structures, systems, or components due to a single specific event or cause, such as a natural phenomenon (earthquake, tornado, flood, etc.), design deficiency, manufacturing flaw, operation and maintenance error, human-induced destructive event, or aging effect.

A design feature added to the design as a standalone structure, system or component (SSC) or added capability to an existing SSC to cope with design extension conditions. Also called additional safety feature.

A performance or safety indicator that is not specified by legislation or regulation and is not a direct measure of performance or safety (safety indicators), but is used to complement the use of these more direct indicators. Note: Complementary indicators are often intermediate parameters from which performance or safety indicators can be derived, but are easier to calculate and monitor (for example, concentration of contaminant releases as a complementary indicator to human exposure to that contaminant). Complementary indicators can be useful in scoping calculations.

Conformity by regulated persons or organizations with the requirements of the Nuclear Safety and Control Act (NSCA), the regulations made under the NSCA, and licences, decisions, certificates and orders made by the CNSC.

Verification activities mostly limited to the review of licensees’ documents and reports. Some examples are quarterly technical reports, annual compliance reports, special reports and documentation related to design, safety analysis, programs and procedures.

An extracted product that contains uranium and that results from the physical or chemical separation of uranium from ore. (Source: Uranium Mines and Mills Regulations )

Note: See also uranium concentrate.

An activity concentration that does not result in an effective dose

• greater than 1 mSv in a year due to a low probability event referred to in the IAEA Safety Standard RS‑G‑1.7 [2]; or
• greater than 10 µSv in a year.

(Source: Nuclear Substances and Radiation Devices Regulations )

Note: The abbreviation µSv means microsievert.

An assessment performed to determine the current performance and condition of a structure, system or component (SSC) (including any age‑related failures or indications of significant material degradation), and to predict the future performance, extent and rate of aging degradation, and residual service life of the SSC.

Maintenance that is planned and performed after identification or diagnosis of a structure, system or component degradation, but before failure occurs. See also predictive maintenance.

See condition-based maintenance.

A characteristic of a structure, system or component (SSC) that can be observed, measured or trended to infer or directly indicate the SSC’s current and future ability to function within acceptance criteria.

Continuous or periodic inspections, measurements or trending of the performance or physical characteristics of structures, systems and components, to indicate current or future performance and the potential for failure.

The process of identifying and documenting the characteristics of a facility’s structures, systems and components (including computer systems and software), and of ensuring that changes to these characteristics are properly developed, assessed, approved, issued, implemented, verified, recorded and incorporated in the facility documentation.

A continuous boundary without openings or penetrations, which prevents the release of radioactive materials out of the enclosed space.

Note 1: For small or research reactors, confinement, or confinement boundary, is the equivalent of a power reactor containment boundary but does not have significant pressure-retaining capability.

Note 2: For packaging and transport of nuclear substances, confinement means preserving criticality safety, and containment means containing radioactive material.

The assembly of fissile material and packaging components intended to preserve criticality safety. (Source: Packaging and Transport of Nuclear Substances Regulations, 2015 )

Note: For reactor facilities, see confinement boundary.

The use of assumptions that make predictions regarding consequences more severe than if best‑estimate assumptions had been used.

Calculations that are designed to over-predict a parameter with the intention that the reality will not be greater than the prediction. These calculations can be based on simplifications of the processes being simulated (the structure of a model) or on limits of data values used in the model.

A method deliberately leading to results that are intended to be limiting relative to specified acceptance criteria.

Has the same meaning as in the IAEA Regulations. (Source: Packaging and Transport of Nuclear Substances Regulations, 2015 )

Note: In the IAEA Regulations, consignee means any person, organization or government that is entitled to take delivery of a consignment.

Has the same meaning as in the IAEA Regulations. (Source: Packaging and Transport of Nuclear Substances Regulations, 2015 )

Has the same meaning as in section 1.4 of the Transportation of Dangerous Goods Regulations. (Source:  Packaging and Transport of Nuclear Substances Regulations, 2015 )

From the IAEA Safety Glossary

A prospective and source related value of individual dose (see dose constraint) or of individual risk (see risk constraint) that is used in planned exposure situations as a parameter for the optimization of protection and safety for the source, and that serves as a boundary in defining the range of options in optimization.

The process of procuring, manufacturing and assembling the components, carrying out civil work, installing and maintaining components and systems, and performing associated tests.

The entity managing the procurement, manufacture and assembly of components, carrying out of civil work, installment and maintenance of components and systems, and performance of associated tests. They may be part of the licensee’s organization or a contracted entity.

The information provided with the licence application for a licence to construct, including the documents to which the application makes reference, once approved by the CNSC.

A method or physical structure designed to prevent or control the release of nuclear, radioactive or hazardous substances. Some examples are:

• for waste management: a barrier system that controls releases to the environment through different chemical and physical applications
• for reactor facilities: see containment structure
• for deep geological disposal: the functions of both the natural barrier (such as the host rock) and the engineered barrier to limit radionuclide releases

OR

With respect to safeguards, means the structural features of a facility, containers or equipment that are used to establish the physical integrity of an area or items (including safeguards equipment or data) and to maintain the continuity of knowledge of the area or items through the prevention of undetected access to, or movement of, nuclear or other material, or interference with the items.

OR

The exercise of force that is sufficient to isolate, contain and/or stop an adversary in order to prevent the theft of nuclear material or sabotage to a vital area until the offsite response force can make an effective intervention.

Structures and components that provide a pressure-retaining barrier to prevent or limit the escape of any radioactive matter that could be released from a nuclear reactor.

For reactor facilities, a physical structure designed to prevent uncontrolled release and dispersion of nuclear substances.

Has the same meaning as in the IAEA Regulations. (Source: Packaging and Transport of Nuclear Substances Regulations, 2015 )

OR

See containment structure.

Contaminant that could be released to the environment as a result of a project and that may change one or more of the environmental components (atmospheric, aquatic, terrestrial).

Has the same meaning as in the IAEA Regulations. (Source: Packaging and Transport of Nuclear Substances Regulations, 2015 )

Note: More generally, contamination refers to nuclear or hazardous substances on surfaces, or within solids, liquids or gases (including the human body), where their presence is unintended or undesirable, or to the process giving rise to their presence in such places.

A radiation detection instrument designed to measure surface contamination; this meter is not designed to measure radiation dose or dose rate.

Predefined sets of actions for response to unauthorized acts indicative of attempted unauthorized removal or sabotage, including threats thereof, designed to effectively counter such acts.

A structured curriculum that maintains and enhances knowledge, skills and safety-related attributes, and that addresses areas such as equipment changes and procedure changes, skill weaknesses, infrequently used and difficult-to-acquire knowledge and skills, and lessons learned from operating experiences. Refresher training, requalification training and update training are also considered continuing training.

See vendor/contractor.

See environmental control.

For exposure devices, a component of a control assembly that attaches the control assembly to the exposure container.

See remote control.

For exposure devices, a component used to attach a drive cable to a source assembly.

For exposure devices, a cable or other mechanical means used to push out or retract a sealed source assembly in an exposure container by remote control.

For exposure devices, the rigid or flexible tube for guiding a control cable by remote control to the exposure container and for providing physical protection to the control cable.

See restricted area.

The controlled nuclear equipment and the parts and components for controlled nuclear equipment referred to in the schedule. (Source: Nuclear Non‑proliferation Import and Export Control Regulations )

See also nuclear and nuclear-related dual-use items.

The controlled nuclear information referred to in the schedule. (Source: Nuclear Non‑proliferation Import and Export Control Regulations )

See also nuclear and nuclear-related dual-use items.

A controlled nuclear substance referred to in the schedule. (Source: Nuclear Non‑proliferation Import and Export Control Regulations )

See also nuclear and nuclear-related dual-use items.

A parameter that is kept within specified limits, and, when varied, influences the margin of subcriticality.

A person who, during an emergency drill or exercise, provides data and messages to the emergency responders, for example, to ensure that the sequence of events is unfolding as per the scenario.

A location that is permanently staffed during periods when the event in question may occur; for example, a control room.

See remote control.

Raschig rings that are periodically removed from service for scheduled measurements and then returned to service after these short test periods.

See reactor operator.

The person in a multi-unit nuclear power plant who is responsible to the plant shift supervisor for ensuring that the main control room staff function safely within his or her authority limits and that the conduct of operations within the main control room is performed in accordance with the plant’s licence, policies and procedures.

A safety and control area (SCA) that covers the implementation of a program to manage workplace safety hazards and to protect workers. This SCA is one of the 14 within the CNSC SCA Framework.

The value attributed to a particular quantity and accepted, sometimes by convention, as having an uncertainty appropriate for a given purpose. For example, the conventionally true value of H_p(d) is established by measuring the free-in-air kerma (or exposure) in a well-defined field with a calibrated instrument and then applying a conversion coefficient to the result. Sometimes also called best estimate; conventional value; reference value.

See conventionally true value.

With respect to fitness for duty, additional training required for a breath alcohol technician who was previously qualified to operate an approved instrument, in order to qualify the technician to operate a different approved instrument. See also approved instrument; breath alcohol technician.

Has the same meaning as in the IAEA Regulations. (Source: Packaging and Transport of Nuclear Substances Regulations, 2015 )

See contaminant of potential concern.

A functional area that groups 8 of the 14 safety and control areas (SCAs) within the CNSC SCA Framework: radiation protection, conventional health and safety, environmental protection, emergency management and fire protection, waste management, security, safeguards and non‑proliferation, and packaging and transport. Other functional areas are “management” and “facility and equipment”.

Accident leading to significant fuel damage. For CANDU reactors, core damage is defined as extensive physical damage of the multiple fuel channels due to overheating leading to loss of core structural integrity.

An expression of the likelihood that an accident could cause core damage.

A lava‑like molten mixture of portions of nuclear reactor core.

Measure taken to eliminate the cause of a detected nonconformity or other undesirable situation to prevent recurrence. See also adaptive management.

Actions that, by means of repair, overhaul or replacement, restore the capability of a failed structure, system or component to perform its defined function within the given acceptance criteria.

An item that is intentionally manufactured or altered to imitate a product without the manufacturer or modifier having the legal right to do so.

The country with which Canada has agreed to accept conditions on the use of the nuclear material received from that country. Note: The country of obligation is not necessarily the country of origin or of supply. The countries of obligation, origin and supply may all be different. For a given quantity of nuclear material, there may be a single country of obligation, multiple countries of obligation, or no foreign obligation. Material that has no specified obligations is referred to as unobligated.

The country where specified nuclear material was mined.

The country from which specified nuclear material was shipped prior to entering Canada.

See remote control.

The use of sealed sources to remotely direct the movement of an industrial radiography pipeline crawler unit.

control rod drive mechanism

Accidents or accident sequences that have a frequency of occurrence equal to or more than one in a million years. This definition applies specifically to nuclear criticality safety.

As defined in the CSA Group publication CSA N292.1, Wet Storage of Irradiated Fuel and Other Radioactive Materials [7], a naturally occurring or human-generated event or event sequence that has a frequency of occurrence equal to or greater than 10^-6 per year.

For a safety analysis, assuming the correct operation of a structure, system or component, or correct operator action.

A search used to determine if a person has a criminal record. The search can be based on name and date of birth or, for much greater assurance, on fingerprints for positive identification.

For exposure devices, a component that is essential to the safe operation of the device, in order to prevent a misconnect or disconnect.

OR

Equipment whose failure will result in complete system failure or functional failure.

A uniform or reasonably homogeneous group of people whose characteristics (such as habits, location or age) cause them to be representative of the more highly exposed individuals, receiving the highest effective dose or equivalent dose (as applicable) than other groups in the exposed population.

See nuclear criticality.

The release of energy as a result of accidental production of a self-sustaining or divergent neutron chain reaction.

See nuclear criticality safety control.

Has the same meaning as in the IAEA Regulations. (Source: Packaging and Transport of Nuclear Substances Regulations, 2015 )

See nuclear criticality safety staff.

See criminal records name check.

control room operator; see reactor operator

See CSA Group.

A standard-setting body that works with the regulator, industry and stakeholders to produce consensus-based Canadian industry standards that may be used by the regulator or industry. Formerly called Canadian Standards Association.

See nuclear criticality safety control.

condenser steam discharge valve

See criticality safety index.

See becquerel.

compliance verification criteria

Protection of digital computer-based systems or components throughout the system’s lifecycle from threats and malicious actions, or from inadvertent actions that result in unintended consequences. Cyber security includes protection from unauthorized, unintended and unsafe modifications to the system, and from unauthorized disclosure and retention of information, software or data associated with the system that could be used to perform malicious or misguided acts that could affect the functionality and performance of the system.

A particle accelerator that speeds up particles in a circular motion until they hit a target at the perimeter of the cyclotron. Some cyclotrons are used to produce medical isotopes.