Establishment of an Authenticated Physical Standard for gamma Spectrometric Determination of the U-235 Content of MTR Fuel and Evaluation of Measurement Procedures. Final Report for the Period 1 December 1975 - 28 February 1978

摘要

Measurements of U-235 content in a standard MTR fuel element were carried out, using scintillation and semi-conductor spectrometers. Three different types of measurement were carried out: a) Comparison of different primary standards among one another and with single fuel plates. b) Calibration of the MTR fuel element as an authenticated physical standard. c) Evaluation of over all errors in assay measurements on MTR fuel elements. The error of the whole assay measurement will be approximately 0.9%. The uranium distribution in the single fuel plates is the original source of error. In the case of equal uranium contents in all fuel plates of one fuel assembly, the error of assay measurements would be about 0.3% relative to the primary standards. (Atomindex citation 11:523456)