PDF GB/T 24247-2009 English
Search result: GB/T 24247-2009
| Standard ID | Contents [version] | USD | STEP2 | [PDF] delivered in | Name of Chinese Standard | Status |
| GB/T 24247-2009 | English | 150 |
Add to Cart
|
0-9 seconds. Auto-delivery.
|
Calibration and usage of ionization chamber systems for assay of radionuclides
| Valid |
PDF Preview: GB/T 24247-2009
GB/T 24247-2009: PDF in English (GBT 24247-2009) GB/T 24247-2009
NATIONAL STANDARD OF THE
PEOPLE’S REPUBLIC OF CHINA
ICS 27.120.01
F 88
Calibration and Usage of Ionization Chamber Systems
for Assay of Radionuclides
(IEC 61145:1992, MOD)
ISSUED ON: JUNE 19, 2009
IMPLEMENTED ON: FEBRUARY 1, 2010
Issued by: General Administration of Quality Supervision, Inspection and
Quarantine;
Standardization Administration of the People’s Republic of
China.
Table of Contents
Foreword ... 3
1 Scope ... 4
2 Normative References ... 4
3 Terms and Definitions ... 4
4 Procedure ... 6
5 Uncertainty Component ... 9
6 Main Factors Causing Measurement Differences ... 10
Foreword
This Standard modifies and adopts IEC 61145:1992 Calibration and Usage of
Ionization Chamber Systems for Assay of Radionuclides (English version).
In comparison with IEC 61145:1992, this Standard has following differences:
---The definition of “accuracy” is modified; the index is modified from 10% to 5%,
and calculated in accordance with the formula of measurement error (see
Chapter 1, 3.1 and 4.6.1);
---reproducible is translated as “repeatable”; “repeatability” is modified from 5% to
2%; the formula of calculated by relative standard deviation is added (see
Chapter 1 and 4.6.2);
---The foreword and introduction part of IEC 61145 are deleted; the description of
“system” in the introduction part is brought into Chapter 1 “Scope”;
---In “Normative References”, Chinese national standards are used to replace IEC
standards quoted in IEC 61145 (Chapter 2);
---In “Terms and Definitions” in Chapter 3, “Uncertainty of Measurement” (3.2) and
“Repeatability (of results of measurements)” (3.3) are added; “shall” and
“should” are deleted;
---Two typical representatives of radionuclide source are added (131I, 60Co); the
calibrated energy range is expanded (4.3.3);
---The title of Chapter 5 is modified from “Error Source” into “Uncertainty
Component”; two components of instrument, “inherent error” and “repeatability”
are added;
---The title of Chapter 6 is modified from “Prompts” into “Main Factors Causing
Measurement Differences”.
This Standard as proposed by China National Nuclear Corporation.
This Standard shall be under the jurisdiction of National Technical Committee on
Nuclear Instruments of Standardization Administration of China.
The drafting organizations of this Standard: Shenzhen Academy of Metrology & Quality
Inspection; Nuclear Industry Standardization Institute.
The main drafters of this Standard: Zhou Yingchun, Li Mingzhao, Xiong Zhenglong,
Xiaochen, Yan Chenchang, Qian Xiaoyan.
Calibration and Usage of Ionization Chamber Systems
for Assay of Radionuclides
1 Scope
This Standard specifies the quantitative technique for the determination of
radionuclides’ activity using various ionization chambers that are currently available.
The application of this Standard is limited to instruments that contain well-type
ionization chambers as detectors. It is a composite system that includes an ionization
chamber and an appropriate circuit in overall connection to it that converts the current
in the ionization chamber into a reading in the unit of activity.
This Standard provides methods to obtain measurement whose accuracy does not
exceed ± 6% and whose repeatability is not more than 2% (generally for radionuclides
larger than 3.7 106 Bq (100 μCi)).
2 Normative References
Through the reference in this Standard, the clauses of the following documents
become clauses of this Standard. In terms of references with a specified date, all the
subsequent modification sheets (excluding the corrected content) or revised versions
are not applicable to this Part. However, the various parties that reach an agreement
in accordance with this Part are encouraged to explore the possibility of adopting the
latest version of these documents. In terms of references without a specified date, the
latest version is applicable to this Part.
GB/T 4960.6-2008 Glossary of Terms for Nuclear Science and Technology - Part 6:
Nuclear Instrumentation
GB/T 4078-2008 Dimension of Sample Planchets, Vials and Test Tubes for
Radioactivity Measurement
3 Terms and Definitions
What is defined in GB/T 4960.6-2008, and the following terms and definitions are
applicable to this Standard.
3.1 Accuracy of Measurement
Accuracy of measurement refers to the degree of consistency between the
measurement result and the conventional true value.
[3.3.34 of GB/T 4960.6-2008]
NOTE: in this Standard, accuracy is expressed in relative error, namely, the quotient of the
difference between the measurement result and the conventional true value
divided by the conventional true value (expressed in percentage).
3.2 Uncertainty of Measurement
Uncertainty of measurement refers to a parameter related to the measurement result
that indicates the degree, to which, the measured value may be reasonable distributed.
NOTE: for example, uncertainty might be a standard deviation (or a given multiple), or a
half-width interval with a given confidence.
[3.3.35 of GB/T 4960.6-2008]
3.3 Repeatability (of results of measurements)
Repeatability (of results of measurements) refers to the degree of consistency of
continuous measurement results of the same physical quantity being measured under
the same measurement conditions.
[3.3.38 of GB/T 4960.6-2008]
NOTE: the calculation of repeatability in this Standard adopts the calculation formula of
relative standard deviation.
3.4 Activity
Activity refers to the quotient of dN divided by dt, where dN is the expected value of
the number of spontaneous nuclear transitions with the time interval dt, namely, A =
dN/dt.
3.5 Calibration
Calibration refers to the process of determining the numerical relationship between the
observed value of the measurement system and the actual quantity measured based
on the standard source within the entire specified uncertainty.
3.6 Simulated Sources
Simulated source generally contains a single or composite long-life radionuclide, which
is selected through photon or particle emission to simulate short-life radionuclide of
interest.
......
Source: Above contents are excerpted from the PDF -- translated/reviewed by: www.chinesestandard.net / Wayne Zheng et al.
|