Published 1991
| Version v1
Book
Design considerations for CDA accommodations
Creators
- 1. Power Reactor and Nuclear Fuel Development Corp., Oarai, Ibaraki (Japan). Oarai Engineering Center
Description
This paper presents a view on the safety design approach among Japanese FBR community focusing on the CDA (core disruptive accident) accommodations, which can be summarized as follows: 1) CDA is classified as beyond design basis accidents; 2) emphasis is placed on the harmonization of prevention and mitigation of the accidents; 3) CDA is to be accommodated in the reactor vessel by the conventional design method taking into maximum account of self-limiting intrinsic mechanisms of the phenomena. To attain the in-vessel retention of CDA consequences, generic and effective measures are suggested in light of the recent increased understanding of the physics. (author)
Additional details
Publishing Information
- Publisher
- Tokyo Inst. of Tech.
- Imprint Place
- Tokyo (Japan)
- Imprint Title
- Proceedings of the symposium on the core disruptive accidents of fast breeder reactors
- Imprint Pagination
- 210 p.
- Journal Page Range
- p. 57-81.
Conference
- Title
- Symposium on the core disruptive accidents of fast breeder reactors.
- Dates
- 27-28 Jul 1990.
- Place
- Tokyo (Japan).
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 23087309
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ATWS; DESIGN; LMFBR TYPE REACTORS; MITIGATION; PROBABILISTIC ESTIMATION; REACTOR CORE DISRUPTION; REACTOR SAFETY; TIME DEPENDENCE
- Descriptors DEC
- ACCIDENTS; BREEDER REACTORS; DESIGN BASIS ACCIDENTS; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; LIQUID METAL COOLED REACTORS; REACTOR ACCIDENTS; REACTORS; SAFETY