Analysis of the Savannah River Reactor Emergency Core Cooling System
Technical Report
·
OSTI ID:5114023
This report presents a detailed analysis of the heat removal capability of the Savannah River reactor emergency core cooling system. The capability of the system is evaluated in terms of its ability to cope with a loss-of-coolant accident or a loss-of-circulation accident. In addition to analyses of the present system design, several possible system improvements have been evaluated. The consequences and likelihood were considered of a rupture in any of the cooling systems of SRP reactors, i.e., the D/sub 2/O primary, H/sub 2/O secondary, and H/sub 2/O emergency cooling systems. Accidents covering a wide range of leak rates were analyzed rather than selecting only the worst conceivable accident, because the degree of protection afforded varies with the leak rates. The emergency core cooling system was analyzed in two modes of operation: (1) all equipment operating as designed and (2) failure of that active component causing the most serious consequences. Calculations apply to emergency cooling of the reactor core design having, under most conditions, the most difficult cooling requirements of any core now in use at Savannah River.
- Research Organization:
- Du Pont de Nemours (E.I.) and Co., Aiken, SC (USA). Savannah River Lab.
- DOE Contract Number:
- AC09-76SR00001
- OSTI ID:
- 5114023
- Report Number(s):
- DPST-70-463; ON: DE84003683
- Country of Publication:
- United States
- Language:
- English
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· Transactions of the American Nuclear Society; (United States)
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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
CONVECTION
ECCS
ENGINEERED SAFETY SYSTEMS
EVALUATION
HEAVY WATER MODERATED REACTORS
K REACTOR
LEAKS
LOSS OF COOLANT
LOSS OF FLOW
NATIONAL ORGANIZATIONS
P REACTOR
PERFORMANCE
PRODUCTION REACTORS
REACTOR ACCIDENTS
REACTOR PROTECTION SYSTEMS
REACTORS
SAVANNAH RIVER PLANT
SPECIAL PRODUCTION REACTORS
US AEC
US DOE
US ERDA
US ORGANIZATIONS
22 GENERAL STUDIES OF NUCLEAR REACTORS
220700 -- Nuclear Reactor Technology-- Plutonium & Isotope Production Reactors
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
CONVECTION
ECCS
ENGINEERED SAFETY SYSTEMS
EVALUATION
HEAVY WATER MODERATED REACTORS
K REACTOR
LEAKS
LOSS OF COOLANT
LOSS OF FLOW
NATIONAL ORGANIZATIONS
P REACTOR
PERFORMANCE
PRODUCTION REACTORS
REACTOR ACCIDENTS
REACTOR PROTECTION SYSTEMS
REACTORS
SAVANNAH RIVER PLANT
SPECIAL PRODUCTION REACTORS
US AEC
US DOE
US ERDA
US ORGANIZATIONS