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Title: PRELIMINARY HAZARDS EVALUATION OF THE ISOLATED COOLANT LOOPS IN THE HWCTR

Abstract

The design features of two isolated coolant loops in the Heavy Water Components Test Reactor (HWCTR) and the effect of these features on reactor safety are described. It is shown that limitations on the operating conditions, backed up by properly chosen safety systems, will permit operation of the loops without adding appreciably to the reactor hazards. (auth)

Authors:
; ; ;
Publication Date:
Research Org.:
Du Pont de Nemours (E.I.) & Co. Savannah River Lab., Aiken, S.C.
OSTI Identifier:
4122086
Report Number(s):
DP-489
NSA Number:
NSA-15-001047
DOE Contract Number:  
AT(07-2)-1
Resource Type:
Technical Report
Resource Relation:
Other Information: Orig. Receipt Date: 31-DEC-61
Country of Publication:
United States
Language:
English
Subject:
REACTOR TECHNOLOGY; COOLANT LOOPS; HEAVY WATER; HWCTR; REACTOR SAFETY; REACTORS; SAFETY

Citation Formats

Arnett, L.M., Parkinson, T.F., Randall, D., and Ross, C.P. PRELIMINARY HAZARDS EVALUATION OF THE ISOLATED COOLANT LOOPS IN THE HWCTR. United States: N. p., 1960. Web. doi:10.2172/4122086.
Arnett, L.M., Parkinson, T.F., Randall, D., & Ross, C.P. PRELIMINARY HAZARDS EVALUATION OF THE ISOLATED COOLANT LOOPS IN THE HWCTR. United States. doi:10.2172/4122086.
Arnett, L.M., Parkinson, T.F., Randall, D., and Ross, C.P. Fri . "PRELIMINARY HAZARDS EVALUATION OF THE ISOLATED COOLANT LOOPS IN THE HWCTR". United States. doi:10.2172/4122086. https://www.osti.gov/servlets/purl/4122086.
@article{osti_4122086,
title = {PRELIMINARY HAZARDS EVALUATION OF THE ISOLATED COOLANT LOOPS IN THE HWCTR},
author = {Arnett, L.M. and Parkinson, T.F. and Randall, D. and Ross, C.P.},
abstractNote = {The design features of two isolated coolant loops in the Heavy Water Components Test Reactor (HWCTR) and the effect of these features on reactor safety are described. It is shown that limitations on the operating conditions, backed up by properly chosen safety systems, will permit operation of the loops without adding appreciably to the reactor hazards. (auth)},
doi = {10.2172/4122086},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1960},
month = {7}
}

Technical Report:

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