Published May 1988
| Version v1
Report
Restricted
Improved reliability of residual heat removal capability in PWRs [pressurized water reactors] as related to resolution of Generic Issue 99
Description
This report summarizes a study performed by Brookhaven National Laboratory for the Reactor and Plant Safety Issues Branch, RES of the US Nuclear Regulatory Commission in pursuit of the resolution of NRC Generic Issue 99. Generic Issue 99 focuses on the risk associated with loss of residual heat removal events at PWRs while shut down. Numerous loss of residual heat removal events have occurred at pressurized water reactors (PWRs) in the USA, which were terminated prior to damaging the reactor core. This study estimates the risk from loss of residual heat removal events and investigates ways of lowering this risk
Availability note (English)
NTIS, PC A08/MF A01 - US Govt. Printing Office;1 as TI88011124.
Files
Restricted
The record is publicly accessible, but files are restricted to users with access.
Additional details
Publishing Information
- Imprint Pagination
- 158 p.
- Report number
- NUREG/CR--5015
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 19093410
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- AFTER-HEAT REMOVAL; PWR TYPE REACTORS; REACTOR CORES; REACTOR SAFETY; RELIABILITY
- Descriptors DEC
- ENRICHED URANIUM REACTORS; POWER REACTORS; REACTOR COMPONENTS; REACTORS; SAFETY; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- BNL-NUREG--52121.