GB/T 4960.5-1996 Terminology of nuclear science and technology Radiation protection and safety of radiation sources
Some standard content:
ICS27.120
National Standard of the People's Republic of China
GB/T4960.5-1996
Terms of Nuclear Science and Technology
Radiation Protection and Safety of Radiation Sources
Glossary of terms: Nuclear science and technologyRadiation protection and safety of radiation sources1996-03-31Promulgated
1996-10-01Implementation
State Administration of Technical Supervision
Subject content and scope of application
General terms
Radiation and sources
Radiation quantities and units
Radiation protection in practice…
Safety of sources
Radiation protection of intervention.
Radiation protection equipment and methods
Radiation monitoring·
10 Radiation Biological effects and occupational health services protection and safety management
Appendix ASome dosimetric quantities defined in ICRP-26 report and still in use (supplement) · Appendix B Chinese index (supplement)
Appendix C
English index (supplement)
100000000
National Standard of the People's Republic of China
Nuclear science and technology terms
Radiation protection and safety of radiation sources
Glossary of terms: Nuclear scienceand technologyRadiation protection and safety of radiation sources1Subject content and scope of application
GB/T4960.5—1996
This standard specifies the basic terms and definitions commonly used in the field of ionizing radiation protection and radiation source safety. This standard applies to all areas involving ionizing radiation and radiation source safety. 2-General terms
2.1 Radioactivity
The property of certain nuclides to spontaneously emit particles or rays, or to emit X-rays after orbital electron capture, or to undergo spontaneous fission.
2.2 Radioactive decay radioactive decay A spontaneous nuclear transition process in which particles or rays are emitted, or orbital electron capture and subsequent X-rays are emitted, or spontaneous nuclear fission occurs.
2.3 Radioactive half-life T/2radioactive half-life The time it takes for a radioactive nuclide to decay to half its activity due to radioactive decay. 2.4 Decay chain decay chain radioactive chain radioactive chain refers to a series of nuclei in which each nucleus is transformed into the next nucleus by radioactive decay (excluding spontaneous fission) until a stable nucleus is formed.
2.5. Radionuclide radionuclide radionuclide radioactive.
2.6 Cosmogenic radionuclide Radionuclides produced by the interaction of cosmic rays with atoms in the atmosphere. 2.7
Primordial radionuclide Radionuclides present in the Earth's crust since the formation of the Earth (including K, 87Rb, and radioactive daughters in the uranium and pyrite decay chains).
2.8 Ionizing event ionizing event
The process by which particles interact with matter to produce ion pairs or ion groups. 2.9 Energy deposition event energy deposition event An event in which an ionized particle or a group of accompanying ionized particles imparts energy to matter in a specified volume. 2.10 (Ionizing) radiation Charged or (and) uncharged particles that can cause ionization events through primary or secondary processes. Approved by the State Administration of Technical Supervision on March 31, 1996, and implemented on October 1, 1996
GB/T4960.5-—1996
In the field of ionizing radiation protection, ionizing radiation is also referred to as radiation. 2.11 Source source
Anything that can cause radiation exposure by, for example, emitting ionizing radiation or releasing radioactive substances. For example, substances that emit hydrogen are sources existing in the environment, irradiation disinfection devices are sources in the practice of food irradiation preservation, X-ray machines can be sources in the practice of radiodiagnosis, and nuclear power plants are sources in the practice of nuclear power generation. 2.12 Irradiation (exposure) exposure
Exposure to ionizing radiation.
2.13 Irradiation irradiation
The process of irradiating people or objects with ionizing radiation emitted by a radioactive source or other radiation source (such as an X-ray machine). 2.14 Practice
Any human activity that introduces new sources of radiation or exposure pathways, or expands the scope of exposed personnel, or changes the exposure pathway network of existing sources, thereby increasing the exposure of people, the possibility of exposure, or the number of people exposed. 2.15 Intervention
Any action aimed at reducing or avoiding exposure or the possibility of exposure caused by sources that are not part of controlled practices or that are out of control due to accidents. 2.16 Radiation protectionradiation protectionradiological protectionThe applied discipline that studies the protection of human beings (which can refer to all human beings, some or individual members of them, and their descendants) from or as little as possible radiation hazards. Sometimes it also refers to the requirements, measures, means and methods used to protect humans from or as little as possible radiation hazards. In a broad sense, radiation includes both ionizing radiation and non-ionizing radiation, the latter such as microwaves, lasers and ultraviolet rays; in a narrow sense, it only includes ionizing radiation. The term radiation protection in this standard refers specifically to ionizing radiation protection. 2.17 Safety (of sources) Ensure the correct operation or utilization of sources, prevent accidents or mitigate the consequences of accidents, so as to protect workers, the public and the environment from excessive radiation hazards.
3 Radiation and sources
3.1 Direct ionizing radiation directly ionizing radiation Charged particles with sufficient kinetic energy that can cause ionization when colliding, such as electrons, protons, alpha particles, heavy ions, etc., are called directly ionizing particles. Radiation composed of directly ionizing particles is called direct ionizing radiation. 3.2 Indirect ionizing radiation indirectly ionizing radiation Neutral particles that interact with matter and can produce directly ionizing particles, such as neutrons and photons, are called indirect ionizing particles. Radiation composed of indirectly ionizing particles is called indirect ionizing radiation. : 3.3 Bremsstrahlung
· Electromagnetic radiation emitted when the electromagnetic field changes the momentum of charged particles. 3.4 Hydrogen daughters radondaughters
Short-lived daughters in the decay products of 22Rn, mainly 213Po(Ra), 214Po(RaB), 214Bi(RaC), 21*Po(RaC). 3.5 Hydrogen daughter alpha potential radondaughterαpotentialenergy The sum of the alpha particle energies released when the hydrogen daughters completely decay into 210Pb(RaD). 3.6 Cosmic radiation cosmic radiation
Ionizing radiation from the sun and outer space, which varies with altitude and latitude. Initial nuclear radiation; early nuclear radiation initialnuclearradiation3.7
Nuclear radiation (including neutrons and radiation) released in a short period of time after a nuclear explosion. This time limit is artificially defined, usually more than ten seconds or one minute.
penetratingradiation
3.8 Penetrating radiation
GB/T4960.5—1996
Radiation with strong penetrating ability in matter. Generally refers to radiation, X-radiation and neutron radiation. 3.9 Strongly penetrating radiation In a uniform unidirectional radiation field, for a given human body orientation, if the ratio of the equivalent dose received by any small area of the sensitive layer of the skin to the effective dose is less than 10, then this radiation is called strong penetrating radiation. 3.10 Weakly penetrating radiation weakly penetrating radiation In a uniform unidirectional radiation field, for a given human body orientation, if the ratio of the equivalent dose received in any small area of the sensitive layer of the skin to the effective dose is greater than 10, then this radiation is called weakly penetrating radiation. 3.11 Radiation quality radiation quality describes the radiation characteristics of the microscopic spatial distribution of energy transfer of charged particles (primary charged ionizing particles or secondary charged particles generated by uncharged ionizing particles) in matter. The linear energy transfer density is one of the methods to describe radiation quality. 3.12 Low LET radiation lowLET radiation Radiation in which the distance between each ionization event directly generated or generated by secondary charged particles is relatively large when measured on the scale of the cell nucleus. Generally refers to Y, X, β radiation and electrons, etc. 3.13 High LET radiation highLET radiation Radiation in which the distance between each ionization event directly generated or generated by secondary charged particles is relatively small when measured on the scale of the cell nucleus. Generally refers to fast neutrons, protons and α particles, etc. 3.14 Radiation source radiationsource
A device or substance that emits or can emit ionizing radiation. 3.15 Natural radiation source naturalradiationsource A naturally occurring source of ionizing radiation. The radiation they produce is also called natural background radiation, which comes from the following three aspects: cosmic radiation, cosmic radionuclides, and primary radionuclides. 3.16 Radioactive aerosol radioactive aerosol A dispersion system formed by tiny solid or liquid particles containing radionuclides in the air or other gases. 3.17 Radioactive fallout radioactive fall-out Dust containing radioactive substances that is formed after a nuclear explosion or a release from a nuclear facility, etc., and gradually settles under the action of gravity and other forces.
3.18 Radioactive effluent radioactive effluence Radioactive aerosol, radioactive gas or liquid radioactive substance discharged into the environment. 3.19 Radioactive contamination radioactive contamination The amount of unwanted radioactive substances present in or on the surface of the substance under consideration exceeds its naturally existing amount and causes technical troubles or hazards.
3.20 Radioactive waste Radioactive waste, radwaste is waste that contains or is contaminated with radionuclides, whose concentration or specific activity is greater than the clean clearance level determined by the regulatory agency, and is not expected to be used again. (This definition is entirely from the management perspective. Materials with radioactivity concentrations equal to or lower than the clean clearance level are still radioactive from a physical point of view, but their radioactive hazards can be ignored). 3.21 Sealed source sealed source
A radioactive source sealed in a shell or a tight covering layer. The shell or covering layer should have sufficient strength so that no radioactive material will be lost under the designed operating conditions and normal wear. 3.22 Unsealed source unsealed source
A radioactive source that is not a sealed source.
3.23 Point (radiation) source point source (of radiation) A radiation source whose linear dimension is much smaller than the measurement distance. 3.24 Non-point (radiation) source extended source (of radiation) GB/T4960.5-1996
The size of the source cannot be ignored relative to the measured or calculated distance, so it cannot be regarded as a point source of radiation. 3.25 Simulated source simulated source
An imitation of a certain radiation source. For a sealed source, its cladding structure and material are exactly the same as those of a real radiation source; the material of its simulated source core is as close as possible to the material of a real radiation source in terms of mechanical, physical and chemical properties, but the radioactive material contained is only a tracer amount.
3.26 Radiation generator
Radiation generator
A device that can generate radiation such as X-rays, neutrons, electrons or other charged particles, which can be used in science, industry or medicine.
3.27 High-energy radiotherapy equipment high energy radiotherapy equipment radionuclide teletherapy equipment and X-ray machines and other types of radiation generators with an operating voltage higher than 300kV. 3.28 Irradiation installations Structures or facilities that contain particle accelerators, X-ray machines or large radiation sources and can produce high-intensity radiation fields. Properly designed structures provide shielding and other protection and are equipped with safety devices (such as interlocks) to prevent accidental entry into high-intensity radiation fields. 3.29 Nuclear fuel cycle nuclear fuel cycle All activities related to nuclear energy production, including mining, milling, processing and enrichment of uranium or thorium, nuclear fuel manufacturing, nuclear reactor operation, nuclear fuel reprocessing, decommissioning and radioactive waste management, as well as any research and development activities related to the above activities.
3.30 Uranium/thorium mining and milling facilities Mine or mill processing uranium/thorium ores Facilities for mining, milling or processing of ores containing thorium or thorium radionuclides. A mine that mines uranium and needle ore refers to any mine that mines ore containing uranium or needle series radionuclides in sufficient quantity and of a grade worthy of mining; or a mine that, when coexisting with other minerals being mined, requires radiation protection measures to be taken in accordance with the regulations of the regulatory authorities.
Uranium and needle ore hydrometallurgy refers to any facility that processes radioactive ores mined in the above mines to produce physical or chemical concentrates. 3.31 Nuclear installation A facility that produces, processes, utilizes, operates, stores or disposes of radioactive materials on a scale that requires safety considerations [including its site, buildings (structures) and equipment]. Such as: uranium processing, enrichment facilities, nuclear fuel manufacturing plants, nuclear reactors (including critical and subcritical devices), research reactors, nuclear power plants, spent fuel storage facilities and nuclear fuel reprocessing plants. 3.32 Radioactive waste management facilities Radioactive waste management facilities Facilities specially designed for the operation, treatment, conditioning, temporary storage or permanent disposal of radioactive waste. 3.33 Installationprocessingradioactivesubstances Any facility that processes radioactive materials with an annual processing volume exceeding 10,000 times the exempted activity concentration. 3.34 Radioactivesourceterm A description of data on the actual or possible release of radioactive materials from a given source. This may include the composition, quantity, rate and mode of release of the released material. 4 Radiation quantities and units
The terms used in radiation protection given in this chapter are defined or quoted in the 1990 recommendations of the International Commission on Radiological Protection (ICRP). For terms on some dosimetric quantities defined in ICRP Publication No. 26 that are still used in my country's radiation protection regulations or standards, see Appendix A (Supplement). 4.1 Dose dose
A measure of the radiation received or "absorbed" by an object. Depending on the context, it can refer to absorbed dose, organ dose, equivalent dose, effective dose, committed equivalent dose and committed effective dose. 4.2 Absorbed dose The quotient obtained by dividing de by dm, namely:
GB/T4960.5--1996
Where: de——the average energy of ionizing radiation imparted to a substance with a mass of dm. 4.3 Absorbed dose rate D = dD/dt
Where: dD-the increment of absorbed dose within the time interval dt. 4.4 Radiation weighting factor Wrradiation weighting factor For the purpose of radiation protection, the factor multiplied by the absorbed dose is used to consider the relative harmful effects of different types of radiation on health. 4.5 Equivalent dose Hr. Requivalent dose The equivalent dose Hr produced by radiation R in an organ or tissue T is the product of the average absorbed dose Dr,r in the organ or tissue T and the radiation weighting factor Wr, that is,
Ht.R=WRD.Rbzxz.net
4.6 Tissue weighting factor Wtissueweightingfactor For the purpose of radiation protection, the factor by which the equivalent dose of an organ or tissue is multiplied is used to take into account the different sensitivities of different organs and tissues to the random effects of radiation. 4.7 Effective dose Eeffectivedose
When the effect under consideration is a stochastic effect, in the case of non-uniform irradiation of the whole body, the sum of the weighted equivalent doses of all tissues or organs of the human body, that is,
Where: Hr
Equivalent dose received by tissue or organ T;
Weighting factor of tissue T.
4.8 Equivalent dose commitment Hcequivalent dose commitment For a specified group, due to a specific event, decision or practice involving radiation risk, the average dose rate (H) received by a certain organ or tissue of each person is integrated over an infinite time period. That is, H. =Hr(t)dt
4.9 Effective dose burden E. effectivedosecommitmentFor a given group of people, the effective dose rate E received per person for an infinite period of time as a result of a specific event, decision or practice involving a risk of radiation, is the integral of the effective dose rate E received per person for an infinite period of time, that is: E.
4.10 Collective dosecollectivedose
For a given group of people, the product of the average dose received by each member of the group and the number of members in the group, where the organs used to determine the doses are specified.
4.11 Collective equivalent doseSrcollectiveequivalentdoseFor a group of people exposed to a given radiation source, the collective equivalent dose of tissue T is defined by the following formula: .H·r.aHt
Where:
Where: N
The number of people receiving equivalent doses between Hr and Hr+dH, which can also be expressed by the following formula: St
The number of people in the ith group receiving an average organ equivalent dose of Hr. GB/T4960.5--1996
4.12 Collective effective dose collective effective dose For a given radiation source, the collective effective dose S of the exposed group is defined as follows: dNaE
Where: N is the number of people in the ith group who receive an average effective dose of E. 4.13 Collective equivalent dose commitment Sc collective equivalent dose commitment For a specified group, the integral of the collective equivalent dose rate S over an infinite period of time due to the exposure that continues in time caused by a given event, decision or practice. That is: Sc =
Sr(t)d
4.14 Collective effective dose commitment collective effective dose commitment For a specified group, the exposure caused by a given event, decision or practice that continues in time is the integral of the collective effective dose rate Se over an infinite time period, that is: Se.c
Se(t)dt
4.15 Incomplete collective dose commitment incomplete collective dose commitment truncated collective dose commitment In the definition of "collective equivalent dose commitment" (see Article 4.13), the upper limit of the time integral (α0) is replaced by a finite time T, and the incomplete (or truncated) collective equivalent dose commitment (incomplete (truncated) collective equivalent dose commitment) is obtained, that is
Sr(t)ds
If T is the duration of a practice, then S.. can be used to predict the future maximum per capita annual collective equivalent dose rate caused by this practice. If the collective equivalent dose rate St(t) in the above formula is replaced by the collective effective dose rate, the incomplete (or truncated) collective effective dose commitment Cincomplete (truncated) collective effective dose commitment is obtained. 4.16 Committed absorbed dose The committed absorbed dose D(t) is defined as:
- the moment of ingestion of radioactive material;
Where: t
D(t)dt
D(t) - the absorbed dose rate at moment t;
the time elapsed after the ingestion of radioactive material. If not specified, t is taken as 50 years for adults and 70 years for children.
4.17 Committed equivalent dose committed equivalent dose H(t) is defined as:
Where: to—the time of ingestion of radioactive material; Hr(t)—the equivalent dose rate of organ or tissue T at time t H(t)dt
—the time elapsed after ingestion of radioactive material. If not specified, 50 years shall be taken for adults and 6 years for children. Ingestion shall be calculated up to 70 years old.
GB/T4960.5—1996
4.18 Committed effective dose committed effective dose E(t) is defined as:
Where: t. —the time of ingestion of radioactive material; E(t)—the effective dose rate at time t;
E(t)dt
—the time elapsed after ingestion of radioactive material. When not specified, 50 years is taken for adults and up to 70 years for children.
4.19 Annual dose annualdose
The sum of the effective dose of external radiation received by workers during one year of work and the committed effective dose produced by the radionuclides ingested during that year.
4.20 Organ dose organdose
The average dose Dr in a specific tissue or organ T of the human body, which is given by the following formula: Ddm
Dr=(1/m）
Where: mrThe mass of the tissue or organ;
Absorbed dose in a mass unit dm.
4.21 Quality factor Qqualityfactor
The coefficient used to express the influence of the microscopic distribution of absorbed dose on the hazard. Its value is specified based on the value of the energy transfer line density in water. For radiation with energy spectrum distribution, the effective value of Q can be calculated. In actual radiation protection, the approximate value of Q can be used according to the type of primary radiation.
4.22 Dose equivalent Hdoseequivalent
The dose equivalent H at a certain point in the tissue is the product of D, Q and N, that is, H=DQN
where: D-absorbed dose at the point;
Q—quality factor of radiation;
N——the product of other correction factors.
4.23 Personal dose equivalent personaldoseequivalent The dose equivalent in the soft tissue at an appropriate depth d below a certain specified point on the human body. Personal dose equivalent applies to both strong penetrating radiation and weak penetrating radiation. For strong penetrating radiation, the recommended depth d=10mm; for weak penetrating radiation, the recommended depth d=0.07mm.
4.24 Deep personal dose equivalent H(d) individualdoseequivalentpenetrating The dose equivalent in the soft tissue at a depth d below a certain specified point when the human body is irradiated with strong penetrating radiation. The recommended value of d is 10 mm, so H,(d) is written as H,(10).
4.25 Superficial individual dose equivalent H,(d) individualdoseequivalentsuperficial The soft tissue dose equivalent at a depth d below a specified point when weakly penetrating radiation irradiates the human body. The recommended value of d is 0.07 mm, so H,(d) is written as H,(0.07).
4.26. Ambient dose equivalent H'(d) ambientdoseequivalent The ambient dose equivalent H'(d) at a point in the radiation field is the dose equivalent produced by the corresponding extended directional field at a depth d on the radius of the anti-directional field within the ICRU sphere. For strongly penetrating radiation, d=10 mm is recommended. 4.27 Directional dose equivalent H'(d, 52) directionaldoseequivalent The directional dose equivalent H\(d, 2) at a point in the radiation field is the dose equivalent produced by the corresponding extended field at a depth d on a radius 7
GB/T4960.5-1996
in the ICRU sphere along the specified direction 2. For weak penetrating radiation, d=0.07mm is recommended. 4.28 Dose albedo dosealbedo
The ratio of the absorbed dose (or equivalent dose) produced by the radiation reflected from the medium to the incident radiation. 4.29 Exposure Xexposure
Where: dQ—The absolute value of the total charge of ions of any sign produced in the air when all the electrons (negative electrons and positive electrons) released by photons in air of mass dm are completely blocked by the air. 4.30 Exposure rate Xexposurerate
xdx/dt
Where: dX—The increment of exposure in the time interval dt. 4.31
(Radioactive) activity Aactivity
At a given moment, the activity A of a certain amount of a certain radionuclide in a specific energy state is the quotient obtained by dividing dN by dt: A=dN/dt
where; dN-the expected value of the number of spontaneous nuclear transitions of the nuclide from the energy state in the time interval dt. 4.32(Radioactive) activity concentration AyactivityconcentrationVolume(Radioactive) activity AvyvolumicactivityThe quotient obtained by dividing the activity A of a substance by the volume V of the substance: Ay=A/V
4.33Mass(Radioactive) activity
massicactivity
Specificactivityspecificactivity
(Radioactive) activity of a substance per unit mass. 4.34Surface(Radioactive) activitysurfaceactivity(Radioactive) activity per unit surface area. 4.35 Particle number density nparticlenumberdensity The number of free particles per unit volume.
4.36 Particle current density J or Sparticlecurrentdensity is a vector whose component perpendicular to any surface is equal to the net number of particles passing through the unit area of the surface per unit time. 4.37 Particle fluence @particlefluencedN The quotient obtained by dividing da:
@=dN/da
Where: dN-The number of particles injected into a sphere with a cross-sectional area of da. 4.38 (Particle) fluence rate Φ (particle) fluencerate The quotient obtained by dividing the particle flux density particlefluxdensityd by dt:
Φ=d@/dt=d°N/dadt
Where: d@-The increase in particle fluence within the time interval dt. 4.39 Quotient of particle radiance Pparticleradiancedp divided by da
P= dp/d=dN/dadtdn
Wherein: dg—particle fluence rate propagating in a solid angle of d2 in a specific direction. 4.40 Quotient of energy (quantity) fluence energyfluencedR divided by da:
GB/T4960.5-1996
WdR/da
Wherein: dR is the radiation energy injected into a sphere with a cross-sectional area of da. Quotient of energy fluence rate
energy flux density energyfluxdensity
dsub divided by dt:
$=d/dt
Wherein dsub
—increment of energy fluence in time interval dt. Energy radiance renergyradiance
du divided by da:
r=dp/do=dR/dadtda
where: d—energy flux rate of particles propagating in a specific direction and within a solid angle of d. 4.433
Energy imparted eenergyimparted
Energy imparted by ionizing radiation to matter in a certain volume: E=ZE-ZE+ZQ
where: EE-
radiation energy entering the volume, that is, the total energy of all charged and uncharged ionized particles entering the volume (excluding rest energy);
—the total energy of all charged and uncharged ionized particles leaving the volume (excluding rest energy); ZE.
ZQ—the sum of the changes in rest energy of all atomic nuclei and elementary particles when any nuclear change occurs in the volume ("+" indicates a decrease, "+" indicates an increase). 4.44 Linear energy (chord), quotient of linear energy e divided by 7:
-Energy imparted to matter in a certain volume in an energy deposition event; where: e-
7-average length of chord in the volume under study. 4.45
5 Specific energy (imparted) Zspecificenergyimpartede quotient divided by m:
Z==e/m
where: e-
-Energy imparted to matter of mass m by ionizing radiation. 4.46 Specific kerma Kkerma
Quotient of dE divided by dm:
K=dEu/dm
where: dEr
The sum of the initial kinetic energies of all charged ionized particles released by uncharged ionized particles in a certain matter of mass dm.
4.47 Kerma rate Kkerma rate
The quotient obtained by dividing dK by dt:
K=dK/dt
Where: dK
-the increment of kerma in the time interval dt. 4.48 Air kerma rate constant Taairkermarateconstants2K. The quotient obtained by dividing by A:
Where: K.
The air kerma rate caused by photons with energy greater than at a point source i of a radioactive nuclide emitting photons with activity A.5-1996
WdR/da
Where: dR is the radiation energy injected into a sphere with a cross-sectional area of da. Energy flux rate
Energy flux density
The quotient obtained by dividing d sub by dt:
$=d/dt
Where: d sub
-the increment of energy fluence in the time interval dt. Energy radiance renergy radiance
du is the quotient obtained by dividing du by da:
r=dp/do=dR/dadtda
Where: d is the energy fluence rate of particles propagating in a specific direction and within a solid angle of d. 4.433
Energy imparted
Energy imparted to matter in a certain volume by ionizing radiation: E=ZE-ZE+ZQ
Where: EE-
Energy of radiation entering the volume, i.e., the sum of the energies of all charged and uncharged ionized particles entering the volume (excluding rest energy);
—the sum of the energies of all charged and uncharged ionized particles leaving the volume (excluding rest energy); ZE.
ZQ—the sum of the changes in rest energy of all nuclei and elementary particles when any nuclear change occurs in the volume (the "+" indicates a decrease, the "+" indicates an increase). 4.44 (String) Linear energy, the quotient obtained by dividing the linear energy ylinealenergye by 7:
—Energy imparted to matter in a certain volume in an energy deposition event; Where: e-
7—the average length of the string in the volume under study. 4.45
5 Specific energy (imparted) Zspecificenergyimpartede divided by m:
Z==e/m
Where: e-
The energy imparted by ionizing radiation to a substance of mass m. 4.46·Specific kermaKkerma
The quotient obtained by dividing dE by dm:
K=dEu/dm
Where: dEr
The sum of the initial kinetic energies of all charged ionized particles released by uncharged ionized particles in a substance of mass dm.
4.47 Specific kerma rateKkerma rate
The quotient obtained by dividing dK by dt:
K=dK/dt
Where: dK
-The increment of specific kerma in the time interval dt. 4.48 Air kerma rate constant Taairkermarateconstants2K. Divided by A to obtain the quotient:
Where: K.
The air kerma rate caused by photons with energy greater than at a point source i of a radioactive nuclide with photon activity A.5-1996
WdR/da
Where: dR is the radiation energy injected into a sphere with a cross-sectional area of da. Energy flux rate
Energy flux density
The quotient obtained by dividing d sub by dt:
$=d/dt
Where: d sub
-the increment of energy fluence in the time interval dt. Energy radiance renergy radiance
du is the quotient obtained by dividing du by da:
r=dp/do=dR/dadtda
Where: d is the energy fluence rate of particles propagating in a specific direction and within a solid angle of d. 4.433
Energy imparted
Energy imparted to matter in a certain volume by ionizing radiation: E=ZE-ZE+ZQ
Where: EE-
Energy of radiation entering the volume, i.e., the sum of the energies of all charged and uncharged ionized particles entering the volume (excluding rest energy);
—the sum of the energies of all charged and uncharged ionized particles leaving the volume (excluding rest energy); ZE.
ZQ—the sum of the changes in rest energy of all nuclei and elementary particles when any nuclear change occurs in the volume (the "+" indicates a decrease, the "+" indicates an increase). 4.44 (String) Linear energy, the quotient obtained by dividing the linear energy ylinealenergye by 7:
—Energy imparted to matter in a certain volume in an energy deposition event; Where: e-
7—the average length of the string in the volume under study. 4.45
5 Specific energy (imparted) Zspecificenergyimpartede divided by m:
Z==e/m
Where: e-
The energy imparted by ionizing radiation to a substance of mass m. 4.46·Specific kermaKkerma
The quotient obtained by dividing dE by dm:
K=dEu/dm
Where: dEr
The sum of the initial kinetic energies of all charged ionized particles released by uncharged ionized particles in a substance of mass dm.
4.47 Specific kerma rateKkerma rate
The quotient obtained by dividing dK by dt:
K=dK/dt
Where: dK
-The increment of specific kerma in the time interval dt. 4.48 Air kerma rate constant Taairkermarateconstants2K. Divided by A to obtain the quotient:
Where: K.
The air kerma rate caused by photons with energy greater than at a point source i of a radioactive nuclide with photon activity A.
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