ANALYSIS OF RADIOACTIVE GAS GENERATED BY THE AGN-201 REACTOR AT THE UNITED STATES NAVAL POSTGRADUATE SCHOOL

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Abstract:

The principal radioactive constituents of the core gas generated by the AGN-201 reactor at the United States Naval Postgraduate School were identified by an analysis of the spectrum of the emitted gamma-rays and by half- life analysis. Also the absolute activities at various times following generation were determined. A scintillation spectrometer with a gating capability was used. Only those radioisotopes still existing in significant quantities twelve hours after generation were identified since sampling the gas at an earlier time was, for the most part, impractical. The results indicate that the radioisotopes Xe133 and Xe135 are the only ones present in significant quantities. Their combined specific activities varied from .17 to .013 microcuries per cc of gas depending upon the age of the gas. It was determined that an upper limit of approximately 0.2 of the activity might be due to the presence of radioactive iodine.

Author(s):
Grissom, Charles C.
Author Organization(s):
NAVAL POSTGRADUATE SCHOOL MONTEREY CA
Descriptive Note:
Master's thesis
Pagination:
0032

Security Markings

DOCUMENT & CONTEXTUAL SUMMARY

Distribution:
Approved For Public Release
Distribution Statement:
Approved For Public Release; Distribution Is Unlimited.

RECORD

Collection: TR
Identifying Numbers
Monitor Series:
NPS
 Subject Terms
Joint Capability Areas:
JCA_6.3.3_Spectrum Management; JCA_6.3_Net Management; JCA_6_Net Centric; JCA_5.3_Planning; JCA_5_Command and Control; JCA_1_Force Support; JCA_1.2.5_Lessons Learned; JCA_4.5.4_Requirements Definition; JCA_4.5_Operational Contract Support
Communities of Interest:
No COI(s) Identified
Descriptor(s):
*THERMAL REACTORS, COMPUTER PROGRAMMING, DETECTORS, GAMMA RAY SPECTRA, GASES, ISOTOPES, PHOTOGRAPHIC IMAGES, PHOTOMULTIPLIER TUBES, RADIOACTIVE DECAY, REACTOR CORES, REACTOR HAZARDS, SCINTILLATION COUNTERS, VENTING, XENON
Field(s)/Group(s):
Nuclear Fission Reactors (Non-Power), Fission Reactor Materials
Keyword(s):
AGN 201 REACTOR SERIES, AGN 201 REACTORS, FORTRAN, FRANTIC COMPUTER PROGRAM
Report Date:
1964 Jan 01