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
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
220700 -- Nuclear Reactor Technology-- Plutonium & Isotope Production Reactors
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
CALCULATION METHODS
CONTAINMENT
DESIGN BASIS ACCIDENTS
DOSES
ENGINEERING
ENRICHED URANIUM REACTORS
FAILURES
FISSION PRODUCT RELEASE
GRAPHITE MODERATED REACTORS
LOSS OF COOLANT
LWGR TYPE REACTORS
MATHEMATICAL MODELS
N-REACTOR
PIPES
PLUTONIUM PRODUCTION REACTORS
POWER REACTORS
PRESSURE TUBES
PRODUCTION REACTORS
RADIATION DOSES
REACTOR ACCIDENTS
REACTORS
RUPTURES
SAFETY ENGINEERING
TUBES
WATER COOLED REACTORS
22 GENERAL STUDIES OF NUCLEAR REACTORS
220700 -- Nuclear Reactor Technology-- Plutonium & Isotope Production Reactors
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
CALCULATION METHODS
CONTAINMENT
DESIGN BASIS ACCIDENTS
DOSES
ENGINEERING
ENRICHED URANIUM REACTORS
FAILURES
FISSION PRODUCT RELEASE
GRAPHITE MODERATED REACTORS
LOSS OF COOLANT
LWGR TYPE REACTORS
MATHEMATICAL MODELS
N-REACTOR
PIPES
PLUTONIUM PRODUCTION REACTORS
POWER REACTORS
PRESSURE TUBES
PRODUCTION REACTORS
RADIATION DOSES
REACTOR ACCIDENTS
REACTORS
RUPTURES
SAFETY ENGINEERING
TUBES
WATER COOLED REACTORS