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    ASTM E1005-03e1

    Standard Test Method for Application and Analysis of Radiometric Monitors for Reactor Vessel Surveillance, E 706(IIIA)
    • 발행일 : 2003-02-10
    • 발행기관 : ASTM
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분야 12.02 : 원자력 (Ⅱ), 태양 및 지열에너지
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1.1 This method describes general procedures for measuring the specific activities of radioactive nuclides produced in radiometric monitors (RMs) by nuclear reactions induced during surveillance exposures for reactor vessels and support structures. More detailed procedures for individual RMs are provided in separate standards identified in and in Refs , . The measurement results can be used to define corresponding neutron induced reaction rates that can in turn be used to characterize the irradiation environment of the reactor vessel and support structure. The principal measurement technique is high resolution gamma-ray spectrometry, although X-ray photon spectrometry and Beta particle counting are used to a lesser degree for specific RMs ().

1.1.1 The measurement procedures include corrections for detector background radiation, random and true coincidence summing losses, differences in geometry between calibration source standards and the RMs, self absorption of radiation by the RM, other absorption effects, and radioactive decay corrections (, ).

1.1.2 Specific activities are calculated by taking into account the time duration of the count, the elapsed time between start of count and the end of the irradiation, the half life, the mass of the target nuclide in the RM, and the branching intensities of the radiation of interest. Using the appropriate half life and known conditions of the irradiation, the specific activities may be converted into corresponding reaction rates ().

1.1.3 Procedures for calculation of reaction rates from the radioactivity measurements and the irradiation power time history are included. A reaction rate can be converted to neutron fluence rate and fluence using the appropriate integral cross section and effective irradiation time values, and, with other reaction rates can be used to define the neutron spectrum through the use of suitable computer programs ().

1.1.4 The use of benchmark neutron fields for calibration of RMs can reduce significantly or eliminate systematic errors since many parameters, and their respective uncertainties, required for calculation of absolute reaction rates are common to both the benchmark and test measurements and therefore are self canceling. The benchmark equivalent fluence rates, for the environment tested, can be calculated from a direct ratio of the measured saturated activities in the two environments and the certified benchmark fluence rate().
국제분류(ICS)코드
페이지수 10
Edition 03e1

이력정보

No. 표준번호 표준명 발행일 상태
1 ASTM E1005-21상세보기 Standard Test Method for Application and Analysis of Radiometric Monitors for Reactor Vessel Surveillance 2021-09-01 표준
2 ASTM E1005-21 REDLINE상세보기 Standard Test Method for Application and Analysis of Radiometric Monitors for Reactor Vessel Surveillance 2021-09-01 표준
3 ASTM E1005-16상세보기 Standard Test Method for Application and Analysis of Radiometric Monitors for Reactor Vessel Surveillance 2016-10-01 구판
4 ASTM E1005-16 REDLINE상세보기 Standard Test Method for Application and Analysis of Radiometric Monitors for Reactor Vessel Surveillance 2016-10-01 구판
5 ASTM E1005-15상세보기 Standard Test Method for Application and Analysis of Radiometric Monitors for Reactor Vessel Surveillance 2015-07-01 구판
6 ASTM E1005-10상세보기 Standard Test Method for Application and Analysis of Radiometric Monitors for Reactor Vessel Surveillance, E 706(IIIA) 2010-01-01 구판
7 ASTM E1005-03e1상세보기 Standard Test Method for Application and Analysis of Radiometric Monitors for Reactor Vessel Surveillance, E 706(IIIA) 2003-02-10 구판
8 ASTM E1005-03상세보기 Standard Test Method for Application and Analysis of Radiometric Monitors for Reactor Vessel Surveillance, E 706(IIIA) 2003-02-10 구판
9 ASTM E1005-97상세보기 Standard Test Method for Application and Analysis of Radiometric Monitors for Reactor Vessel Surveillance, E 706(IIIA) 1997-06-10 구판

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