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Title: ANALYSIS OF FUEL ELEMENT CORE BLANKS FOR ARGONNE LOW POWER REACTOR BY GAMMA COUNTING

Abstract

A technique based on a determinaiion of the differential counting rate exhibited by the 184-kev gamma radiation associated with the decay of U/sup 235/ was developed for the determination of the U/sup 235/ content in Argonne Low Power Reactor fuel element core blanks. The Argonne Low Power Reactor core blanks were an aluminum-highly enriched uranium alloy containing 17.5 weight per cent uranium (approximately 4 g U/sup 235/) having the following dimensions: length, 6.875 inches, width, 3.31 inches, and thickness, 0.200 inch. The gamma- ray spectrum emitied by uranium is rather complex. Using a scintillation spectrometer and scanning the spectrum, the energy is found to be concentrated primarily in two regions, at 184 and 90 kev. The 184-kev gamma rays result primarily from the decay of U/sup 235/ The gammas in the 90-kev region result from the U/sup 235/ decay and daughter products of U/sup 238/ and U/sup 235/. Using a pulse-height analyzer, it is possibie to select the desired radiation emitted from the source and determine the counting rate for a given source. In this work the 184-kev gamma radiation was counted to determine the amount of U/ sup 235/ present in the individual core blanks. (auth)

Authors:
;
Publication Date:
Research Org.:
Argonne National Lab., Lemont, Ill.
OSTI Identifier:
4206558
Report Number(s):
ANL-5944
NSA Number:
NSA-14-006034
DOE Contract Number:  
W-31-109-ENG-38
Resource Type:
Technical Report
Resource Relation:
Other Information: Orig. Receipt Date: 31-DEC-60
Country of Publication:
United States
Language:
English
Subject:
REACTOR TECHNOLOGY; ALPR; ALUMINUM ALLOYS; DECAY; ENRICHMENT; FUEL ELEMENTS; GAMMA DETECTION; GAMMA RADIATION; POWER PLANTS; PULSE ANALYZERS; QUANTITATIVE ANALYSIS; QUANTITY RATIO; REACTOR CORE; SCINTILLATION COUNTERS; URANIUM 235; URANIUM ALLOYS

Citation Formats

McGonnagle, W.J., and Perry, R.B. ANALYSIS OF FUEL ELEMENT CORE BLANKS FOR ARGONNE LOW POWER REACTOR BY GAMMA COUNTING. United States: N. p., 1959. Web. doi:10.2172/4206558.
McGonnagle, W.J., & Perry, R.B. ANALYSIS OF FUEL ELEMENT CORE BLANKS FOR ARGONNE LOW POWER REACTOR BY GAMMA COUNTING. United States. doi:10.2172/4206558.
McGonnagle, W.J., and Perry, R.B. Tue . "ANALYSIS OF FUEL ELEMENT CORE BLANKS FOR ARGONNE LOW POWER REACTOR BY GAMMA COUNTING". United States. doi:10.2172/4206558. https://www.osti.gov/servlets/purl/4206558.
@article{osti_4206558,
title = {ANALYSIS OF FUEL ELEMENT CORE BLANKS FOR ARGONNE LOW POWER REACTOR BY GAMMA COUNTING},
author = {McGonnagle, W.J. and Perry, R.B.},
abstractNote = {A technique based on a determinaiion of the differential counting rate exhibited by the 184-kev gamma radiation associated with the decay of U/sup 235/ was developed for the determination of the U/sup 235/ content in Argonne Low Power Reactor fuel element core blanks. The Argonne Low Power Reactor core blanks were an aluminum-highly enriched uranium alloy containing 17.5 weight per cent uranium (approximately 4 g U/sup 235/) having the following dimensions: length, 6.875 inches, width, 3.31 inches, and thickness, 0.200 inch. The gamma- ray spectrum emitied by uranium is rather complex. Using a scintillation spectrometer and scanning the spectrum, the energy is found to be concentrated primarily in two regions, at 184 and 90 kev. The 184-kev gamma rays result primarily from the decay of U/sup 235/ The gammas in the 90-kev region result from the U/sup 235/ decay and daughter products of U/sup 238/ and U/sup 235/. Using a pulse-height analyzer, it is possibie to select the desired radiation emitted from the source and determine the counting rate for a given source. In this work the 184-kev gamma radiation was counted to determine the amount of U/ sup 235/ present in the individual core blanks. (auth)},
doi = {10.2172/4206558},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1959},
month = {12}
}