ISO 21909-2:2021 パッシブ中性子線量測定システム — Part 2: 職場における個人線量測定システムの適格性評価の方法論と基準 | ページ 6

3.1.1

検出器

放射線検出器

入射電離放射線エネルギーを指示および/または測定に適した信号に変換するために使用される装置または物質

[出典:IEC 60050-394:2007, 394-24-01, modified — 「検出器」という用語が最初の優先用語として追加された]

3.1.2

線量計

線量計

与えられたシステムで吸収線量または線量当量を測定するために使用できる、放射線に対する再現可能で測定可能な反応を有する装置。

[出典:ISO 12749-2:2013, 5.5]

3.1.3

個人線量計

個人線量当量（レート）を測定するように設計されたメーター

注記1：個人線量計は、胴体（全身個人線量計）、四肢（四肢個人線量計）、または眼のレンズの近く（眼レンズ線量計）に装着することができます。

[出典:ISO 29661:2012, 3.1.21]

3.1.4

個別モニタリングサービス

IM

3.1.5

線量測定システム

吸収線量又は線量当量の測定に使用されるシステムで、線量計、測定機器及びそれらに関連する参照標準、及びシステムの使用手順からなる。

[SOURCE:ISO 12749-4:2015, 3.1.3, modified — 定義の文言が若干変更された.]

3.2.1

dose equivalent

H

Note 1 to entry: The unit of dose equivalent is joule per kilogram (J·kg⁻¹), and its special name is sievert (Sv).

[SOURCE:ISO 80000-10:2019, 10-83, modified — Note 1 to entry added.]

3.2.2

neutron fluence

Note 1 to entry: The unit of neutron fluence is m⁻², a frequently unit used is cm⁻².

[SOURCE:ISO 80000-10:2019, 10-43, modified — the wording of the definition was slightly modified.]

3.2.3

energy distribution of the neutron fluence

Note 1 to entry: The SI unit of the energy distribution of the neutron fluence is (m⁻²·J⁻¹); a widely-used unit is (cm⁻²·MeV⁻¹).

Note 2 to entry: The energy distribution of the neutron fluence rate ϕ_E is the quotient of dΦ_E by dt ここで, dΦ_E is the increment of the energy distribution of the fluence in time interval dt. The unit is (m⁻²·J⁻¹·s⁻¹); a widely-used unit is (cm⁻²·MeV⁻¹·s⁻¹).

3.2.4

energy and direction distribution of the neutron fluence

Note 1 to entry: The SI unit of the energy and direction distribution of the neutron fluence is m⁻²·J⁻¹·sr⁻¹; a widely-used unit is (cm⁻²·MeV⁻¹·sr⁻¹).

Note 2 to entry: The energy and direction distribution of the neutron fluence rate by dt ここで, dΦ_E,Ω is the increment of the energy and direction distribution of the fluence in time interval dt. The unit is (m⁻²·J⁻¹·sr⁻¹·s⁻¹); a widely-used unit is (cm⁻²·MeV⁻¹·sr⁻¹·s⁻¹).

3.2.5

personal dose equivalent

H_p(d)

dose equivalent in soft tissue at an appropriate depth, d, below a specified point on the human body

Note 1 to entry: The unit of personal dose equivalent is joule per kilogram (J·kg⁻¹) and its special name is sievert (Sv).

Note 2 to entry: The specified point is usually given by the position where the individual’s dosimeter is worn.

[SOURCE:ICRP 103:2007]

3.2.6

ambient dose equivalent

H*(10), H’(0,07) or H’(3)

dose equivalent that would be produced by the corresponding aligned and expanded field in the ICRU sphere at a depth, d, on the radius opposing the direction of the aligned field

[SOURCE:IAEA – Radiation Protection and Safety of Radiation Sources: International Basic Safety Standards - Interim Edition IAEA Safety Standards Series GSR Part 3, 2011]

3.2.7

conversion coefficient

h_pΦ (10,E,α)

quotient of the personal dose equivalent at 10 mm depth, H_p(10), and the neutron fluence, Φ, at a point in the radiation field used to convert neutron fluence into the personal dose equivalent at 10 mm depth in the ICRU tissue slab phantom ここで, E is the energy of the incident neutrons impinging on the phantom at an angle α

Note 1 to entry: The unit of the conversion coefficient is Sv⋅m². A commonly used unit of the conversion coefficient is pSv⋅cm².

3.3.1

conventional true value for the neutron personal dose equivalent

H^conv

quantity value attributed by agreement to a quantity for a given purpose

Note 1 to entry: The conventional value H^conv is the best estimate of the quantity to be measured, determined by a primary standard or a secondary or working measurement standard which are traceable to a primary standard.

Note 2 to entry: in this document, the quantity is the neutron personal dose equivalent.

[SOURCE:ISO/IEC Guide 99:2007, 2.12, modified — the term was changed.]

3.3.2

calibration

operation that, under specified conditions, in a first step, establishes a relation between the quantity values with measurement uncertainties provided by measurement standards and corresponding readings with associated measurement uncertainties and, in a second step, uses this information to establish a relation for obtaining a measurement result from an indication

Note 1 to entry: Calibration may be expressed by a statement, calibration function, calibration diagram, calibration curve, or calibration table. In some cases, it may consist of an additive or multiplicative correction of the indication with associated measurement uncertainty.

Note 2 to entry: Calibration should not be confused with adjustment of a measuring system, often mistakenly called “self‑calibration”, or with verification of calibration.

Note 3 to entry: Often, the first step alone in the above definition is perceived as being calibration.

[SOURCE:ISO/IEC Guide 99:2007, 2.39]

3.3.3

calibration factor

N

Note 1 to entry: mathematical functions, in some cases families of functions, can be used to provide calibration factors over a range of conditions. Several different calibration functions can be defined for the same dosimetry system and possibly be used for different conditions of exposure.

3.3.4

correction factor or function

numerical value or function by which the indication is multiplied to compensate for the deviation of measurement conditions from reference conditions or for a systematic effect

Note 1 to entry: In this document, it corresponds to the factor or function, noted k_n,E,Ω, defined for a specific workplace field, that is applied to the value of the measured dose equivalent in order to take into account the systematic effect induced by the dose response of the dosimetry system.

[SOURCE:ISO 29661:2012, 3.1.9, modified — the wording of the definition was slightly modified.]

3.3.5

measured dose equivalent

H_M

Note 1 to entry: More elaborate algorithms may also be used.

3.3.6

phantom

object constructed to simulate the scattering and absorption properties of the human body for a given ionizing radiation

Note 1 to entry: For calibrations for whole body radiation protection considerations, the ISO water slab phantom is employed. It is made with polymethyl metacrylate (PMMA) walls (front wall 2,5 mm thick, other walls 10 mm thick), of outer dimensions 30 cm x 30 cm x 15 cm and filled with water.

Note 2 to entry: In the cases of very non-uniform irradiation conditions, an extremity cylinder, pillar or rod phantom may be used as described in ICRU report 66.

[SOURCE:ISO 12749-2: 2013, 4.1.6.1 modified — Notes 1 and 2 to entry added]

3.3.7

reading

M

quantitative indication of a detector or dosemeter when it is read out, generally corrected for background, ageing, fading and non-linearity of the process or the read out system

3.3.8

dose equivalent response

response

R

Note 1 to entry: The reading, M, is converted into dose equivalent, H_M, by multiplying M by an appropriate conversion coefficient or by using a more elaborate algorithm.

Note 2 to entry: In this document, the quantity is personal dose equivalent:

Note 3 to entry: In this document, for the sake of brevity, H_M = H is used.

Note 4 to entry: The reciprocal of the response at reference conditions is equal to the calibration coefficient.

Note 5 to entry: In radiation metrology, the term response, abbreviated for this application from “response characteristic” (VIM), is defined as the ratio of the reading, M, of the instrument, to the value of the quantity to be measured by the instrument, for a specified type, energy and direction distribution of radiation. It is necessary, in order to avoid confusion, to state the quantity to be measured, e.g. the “fluence response” is the response with respect to the fluence, the “dose equivalent response” is the response with respect to dose equivalent.

[SOURCE:ISO 8529‑3:1998, 3.2.10, modified]