Boron dilution reactivity transients, an overview of efforts
Creators
- 1. Office of Nuclear Reactor Regulation, United States Nuclear Regulatory Commission (United States)
Description
The US NRC staff reviewed several studies concerning rapid boron dilution during shutdown and SBLOCA events. Probabilistic analysis indicates that a rapid boron dilution event has a low frequency of occurrence. However, several potential mechanisms could lead to such an event. No three-dimensional (nuclear and hydraulic) analyses have been performed in recent years; also, analyses such as those reported in the paper are subject to considerable uncertainty, particularly regarding mixing. Consequently, these analyses must be viewed as conservative analyses. It is believed that the events reported can be prevented by the use of appropriate procedures which anticipate the possibility of dilution in various recognized situations and prevent it, or prevent the inappropriate starting of pumps until suitable mixing procedures are carried out
Additional details
Publishing Information
- Imprint Title
- Proceedings of a specialist meeting on boron reactivity transients
- Imprint Pagination
- 459 p.
- Journal Page Range
- p. 83-93
- Report number
- NEA-CSNI-R--1996-3
Conference
- Title
- Specialist meeting on boron reactivity transients
- Dates
- 18-20 Oct 1995
- Place
- State College, PA (United States)
INIS
- Country of Publication
- Nuclear Energy Agency of the OECD (NEA)
- Country of Input or Organization
- Nuclear Energy Agency of the OECD (NEA)
- INIS RN
- 43012304
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ACCIDENT MANAGEMENT; BORON; DILUTION; PWR TYPE REACTORS; REACTIVITY INSERTIONS; REACTOR ACCIDENTS; REACTOR COOLING SYSTEMS; REACTOR KINETICS; REACTOR OPERATION; REACTOR SAFETY; REACTOR SHUTDOWN; RISK ASSESSMENT; SAFETY ANALYSIS; THERMAL HYDRAULICS; TRANSIENTS; US NRC; USA
- Descriptors DEC
- ACCIDENTS; COOLING SYSTEMS; DEVELOPED COUNTRIES; ELEMENTS; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; FLUID MECHANICS; HYDRAULICS; KINETICS; MANAGEMENT; MECHANICS; NATIONAL ORGANIZATIONS; NORTH AMERICA; OPERATION; POWER REACTORS; REACTOR COMPONENTS; REACTORS; SAFETY; SEMIMETALS; SHUTDOWN; THERMAL REACTORS; US ORGANIZATIONS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 9 refs.
- Secondary number(s)
- OCDE-GD--97-117