Analysis of the Savannah River Reactor Emergency Core Cooling System
Description
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 D2O primary, H2O secondary, and H2O 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
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS, PC A11/MF A01; 1 as DE84003683.
Files
Additional details
Publishing Information
- Imprint Pagination
- 237 p.
- Report number
- DPST--70-463
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 15062074
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- CONVECTION; ECCS; K REACTOR; LEAKS; LOSS OF COOLANT; LOSS OF FLOW; P REACTOR; PERFORMANCE; PRODUCTION REACTORS; SAVANNAH RIVER PLANT
- Descriptors DEC
- ACCIDENTS; ENERGY TRANSFER; HEAT TRANSFER; HEAVY WATER MODERATED REACTORS; NATIONAL ORGANIZATIONS; REACTOR ACCIDENTS; REACTOR PROTECTION SYSTEMS; REACTORS; SPECIAL PRODUCTION REACTORS; US AEC; US DOE; US ERDA; US ORGANIZATIONS