Improvement of analysis technology for high temperature gas-cooled reactor by using data obtained in high temperature engineering test reactor
Creators
- 1. Japan Atomic Energy Agency, Oarai, Ibaraki (Japan)
Description
The Very High Temperature Reactor (VHTR) system, which is one of generation IV reactors, is the high temperature gas-cooled reactor (HTGR) with capabilities of hydrogen production and high efficiency electricity generation. The High Temperature Engineering Test Reactor (HTTR) is the first HTGR in Japan. The HTTR achieved full power of 30 MW at a reactor outlet coolant temperature of about 950degC in April, 2004 during the 'rise-to-power tests' confirming the reactor performance. The safety demonstration tests by using the HTTR started from 2002 and are under going to demonstrate inherent safety features of HTGRs. The experimental data obtained in these tests are inevitable to design the VHTR with high cost performance. The analytical models validated through these tests in the HTTR are applicable to precise simulation of an HTGR performance and can contribute to the research and development of the VHTR. (author)
Additional details
Publishing Information
- Journal Title
- Journal of Power and Energy Systems
- Journal Volume
- 2
- Journal Issue
- 1
- Journal Page Range
- p. 83-91
- ISSN
- 1881-3062
Conference
- Title
- 15. international conference on nuclear engineering
- Acronym
- ICONE-15
- Dates
- 22-26 Apr 2007
- Place
- Nagoya, Aichi (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 39117140
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- A CODES; DATA ANALYSIS; DESIGN; DUAL-PURPOSE POWER PLANTS; HEAT EXCHANGERS; HTGR TYPE REACTORS; HTTR REACTOR; HYDROGEN PRODUCTION; PERFORMANCE; PERFORMANCE TESTING; POWER GENERATION; REACTOR KINETICS; SAFETY ANALYSIS
- Descriptors DEC
- COMPUTER CODES; ENRICHED URANIUM REACTORS; EXPERIMENTAL REACTORS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HELIUM COOLED REACTORS; HTGR TYPE REACTORS; KINETICS; POWER PLANTS; REACTORS; RESEARCH AND TEST REACTORS; TESTING
Optional Information
- Notes
- 6 refs., 8 figs.