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U.S. Department of Energy
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Confinement response and dose calculations for the hypothetical accident for N Reactor

Technical Report ·
OSTI ID:6221841
A study of a spectrum of pipe break accidents was made for N-Reactor as part of the accident analysis for the N-Reactor Updated Safety Analysis Report (NUSAR). From this selection of accidents, a list was made of those pipe breaks which would represent the most severe consequences in terms of building pressure and temperature transients and in terms of accident-related doses. Those accidents which were considered solely in terms of their temperature and pressure effects on the confinement structures of N-Reactor are discussed in Section 2 of Chapter 6 of NUSAR. The remaining group of accidents which have a potential release of airborne fission products to the environs with offsite doses and doses to personnel in the control room were further broken down into the following two groups: (1) Single pressure tube accidents which result in fission product release from only the fuel in one of 1003 pressure tubes. The nature of these accidents, due to N Reactor design, cannot result in loss of cooling and subsequent failure of fuel elements in any of the other pressure tubes. (2) Large pipe breaks in the reactor coolant system (RCS) which result in a complete blowdown and loss of reactor coolant.
Research Organization:
United Nuclear Industries, Inc., Richland, WA (USA)
DOE Contract Number:
EY-76-C-06-1857
OSTI ID:
6221841
Report Number(s):
UNI-669
Country of Publication:
United States
Language:
English