Published 2005
| Version v1
Computer medium
Spatial-time-dependence of thermal feedback reactivity during control-rod withdrawal test using the HTTR
- 1. Japan Atomic Energy Research Inst., Oarai, Ibaraki (Japan). Oarai Research Establishment
Description
The control-rod withdrawal test using the High Temperature Engineering Test Reactor (HTTR) was performed as the reactivity insertion test in the safety demonstration test. In order to take the spatial dependence of the temperature coefficient during the transient into the thermal feedback of the dynamic analysis code, we produced the spatial temperature coefficient of the HTTR and adopted it to the analysis of the control-rod withdrawal test. As the result, the reactor power transient using the spatial temperature coefficient agreed well with the experimental result by restraining the power transient overestimating at the preliminary analysis using the power temperature coefficient. (author)
Additional details
Publishing Information
- Publisher
- Atomic Energy Society of Japan
- Imprint Place
- Tokyo (Japan)
- Imprint Title
- GLOBAL 2005: Proceedings of the international conference on nuclear energy systems for future generation and global sustainability
- Imprint Pagination
- [2562 p.]
- Journal Page Range
- [6 p.]
Conference
- Title
- International conference on nuclear energy systems for future generation and global sustainability
- Acronym
- GLOBAL 2005
- Dates
- 9-13 Oct 2005
- Place
- Tsukuba, Ibaraki (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 37044239
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- C CODES; COMPUTER CALCULATIONS; D CODES; FEEDBACK; HTTR REACTOR; M CODES; MEETINGS; REACTIVITY INSERTIONS; ROD EJECTION ACCIDENTS; SAFETY ANALYSIS; SPACE DEPENDENCE; TEMPERATURE COEFFICIENT; TEMPERATURE DEPENDENCE; TESTING; TIME DEPENDENCE; TRANSIENTS
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; ENRICHED URANIUM REACTORS; EXPERIMENTAL REACTORS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HELIUM COOLED REACTORS; HTGR TYPE REACTORS; REACTIVITY COEFFICIENTS; REACTOR ACCIDENTS; REACTORS; RESEARCH AND TEST REACTORS
Optional Information
- Notes
- This CD-ROM can be used for WINDOWS 9x/NT/2000/ME/XP, MACINTOSH; Acrobat Reader is included; Data in PDF format, Folder Name GL1XX, Paper ID GL151DF.pdf; 6 refs., 9 figs., 3 tabs.