Published 1981
| Version v1
Book
A post-TMI look at boiling-water reactor plant protection
- 1. General Electric Co., San Jose, CA (USA)
Description
This paper presents the results of a General Electric (GE) evaluation of the Boiling Water Reactor-6 (BWR/6) performed following the March 1979 accident at the Three Mile Island (TMI) nuclear plant. It is shown that the BWR/6 is highly resistant to plant damage or significant off-site radiological releases resulting not only from 'TMI-type' events, but also from a broad spectrum of degraded events ranging from transient events with no pipe break to large pipe break accidents. BWR/6 post-TMI design improvements are described as well as BWR/6 features which respond to longer-term design trends emerging in the aftermath of Three Mile Island. (author)
Additional details
Publishing Information
- Publisher
- IAEA.
- Imprint Place
- Vienna
- ISBN
- 92-0-020381-7
- Imprint Title
- Current nuclear power plant safety issues
- Imprint Pagination
- 599 p.
- Series
- Proceedings series.
- Journal Page Range
- v. 3 p. 103-120.
Conference
- Title
- International conference on current nuclear power plant safety issues.
- Dates
- 20 - 24 Oct 1980.
- Place
- Stockholm, Sweden.
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 13680595
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S61: RADIATION PROTECTION AND DOSIMETRY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CONTAINMENT SYSTEMS; DIRECT CYCLE COOLING SYSTEMS; EMERGENCY PROVISIONS; FISSION PRODUCT RELEASE; GE STANDARD REACTOR; PERFORMANCE; PLANNING; REACTOR ACCIDENTS; REACTOR OPERATORS; REACTOR PROTECTION SYSTEMS; REACTOR SAFETY; RELIABILITY; SYSTEMS ANALYSIS
- Descriptors DEC
- ACCIDENTS; BWR TYPE REACTORS; CONTAINMENT; COOLING SYSTEMS; ENRICHED URANIUM REACTORS; PERSONNEL; POWER REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; SAFETY; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- IAEA-CN--39/112.