Published 2007
| Version v1
Miscellaneous
Summary of a Code Case N-499-1 and Estimation Program
Creators
- 1. Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)
Description
Korea Atomic Energy Research Institute (KAERI) has been developing a VHTR (Very High Temperature Reactor). The behavior of materials at a high temperature is quite different from that at a normal operating temperature in commercial plants. For the behavior evaluation of materials used at a high temperature, several codes are being studied. One of these is the Code Case N-499-1 of ASME Section III. In this study, the contents of the Code Case N-499-1 are introduced. The program developed to estimate the allowable cumulative time based on the Code Case N- 499-1 is also introduced
Additional details
Publishing Information
- Publisher
- KNS
- Imprint Place
- Daejeon (Korea, Republic of)
- Imprint Title
- Proceedings of the KNS spring meeting
- Imprint Pagination
- [1 CD-ROM]
- Journal Page Range
- [2 p.]
Conference
- Title
- 2007 spring meeting of the KNS
- Dates
- 10-11 May 2007
- Place
- Jeju (Korea, Republic of)
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 38113175
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- C CODES; CREEP; EVALUATION; FATIGUE; VHTR REACTOR
- Descriptors DEC
- COMPUTER CODES; ENRICHED URANIUM REACTORS; EXPERIMENTAL REACTORS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HELIUM COOLED REACTORS; HTGR TYPE REACTORS; MECHANICAL PROPERTIES; POWER REACTORS; REACTORS; RESEARCH AND TEST REACTORS; THERMAL REACTORS
Optional Information
- Notes
- 2 refs, 4 figs