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Title: A METHOD OF DETERMINING THE INTERMEDIATE ENERGY NEUTRON DOSE

Abstract

The intermediate energy neutron flux existing outside the biological shielding of reactors has not been studied to any great extent previous to this time, because of the lack of an instrument capable of detecting neutrons in the intermediate energy range. The instrument used at the MTR utilizes polyethylene spheres of various sizes to give different amounts of moderation and absorption to the impinging neutrons. A procedure for the approximate determination of the relative number of intermediate energy and fast neutrons is given. By graphical methods the following information is obtained: (1) fraction of intermediate neutrons, (2) fraction of fast neutrons, and (3) the approximate average energy of the fast neutrons. Since the instrument described can be used to determine the thermal neutron flux independent of intermediate and fast fluxes, only one instrument is required to determine the neutron flux in all three energy ranges. Dose calculations indicate the intermediate range neutrons give a dose greater than the dose delivered by fast neutrons around the MTR-ETR reactors under normal operating conditions. (auth)

Authors:
Publication Date:
Research Org.:
Phillips Petroleum Co. Atomic Energy Div., Idaho Falls, Idaho
OSTI Identifier:
4838516
Report Number(s):
IDO-16655
NSA Number:
NSA-15-030206
DOE Contract Number:  
AT(10-1)-205
Resource Type:
Technical Report
Resource Relation:
Other Information: Orig. Receipt Date: 31-DEC-61
Country of Publication:
United States
Language:
English
Subject:
REACTOR TECHNOLOGY; ABSORPTION; DIAGRAMS; ENERGY; EPITHERMAL NEUTRONS; EQUATIONS; ETR; FAST NEUTRONS; INSTRUMENTS; MATERIALS TESTING; MODERATORS; MTR; NEUTRON DETECTION; NEUTRON FLUX; NEUTRONS; POLYETHYLENES; RADIATION DOSES; REACTORS; SHIELDING; SPHERES; THERMAL NEUTRONS

Citation Formats

Hankins, D.E. A METHOD OF DETERMINING THE INTERMEDIATE ENERGY NEUTRON DOSE. United States: N. p., 1961. Web. doi:10.2172/4838516.
Hankins, D.E. A METHOD OF DETERMINING THE INTERMEDIATE ENERGY NEUTRON DOSE. United States. doi:10.2172/4838516.
Hankins, D.E. Fri . "A METHOD OF DETERMINING THE INTERMEDIATE ENERGY NEUTRON DOSE". United States. doi:10.2172/4838516. https://www.osti.gov/servlets/purl/4838516.
@article{osti_4838516,
title = {A METHOD OF DETERMINING THE INTERMEDIATE ENERGY NEUTRON DOSE},
author = {Hankins, D.E.},
abstractNote = {The intermediate energy neutron flux existing outside the biological shielding of reactors has not been studied to any great extent previous to this time, because of the lack of an instrument capable of detecting neutrons in the intermediate energy range. The instrument used at the MTR utilizes polyethylene spheres of various sizes to give different amounts of moderation and absorption to the impinging neutrons. A procedure for the approximate determination of the relative number of intermediate energy and fast neutrons is given. By graphical methods the following information is obtained: (1) fraction of intermediate neutrons, (2) fraction of fast neutrons, and (3) the approximate average energy of the fast neutrons. Since the instrument described can be used to determine the thermal neutron flux independent of intermediate and fast fluxes, only one instrument is required to determine the neutron flux in all three energy ranges. Dose calculations indicate the intermediate range neutrons give a dose greater than the dose delivered by fast neutrons around the MTR-ETR reactors under normal operating conditions. (auth)},
doi = {10.2172/4838516},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1961},
month = {3}
}