Present status of HTTR project in Japan
Creators
- 1. Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). HTTR Designing Lab.
Description
In Japan, the research and development on the HTR had been carried out for more than fifteen years as the multi-purpose VHTR program for direct utilization of nuclear process heat such as nuclear steel making. Recently, reflecting the change of social and energy situation and with no incentives for industries to introduce such in the near future, the JAERI has changed them for more basic 'HTTR program' to establish the HTR technology basis and upgrade them. At the request of the STA the Reactor Safety Research Association has reviewed the safety evaluation guideline and started the work on the establishment of general design criteria and design code or guide for graphite and high-temperature structure of the HTTR. Construction permit of the HTTR will be issued by the Government early in 1990. (orig./DG)
Additional details
Publishing Information
- Imprint Title
- Proceedings of the workshop on structural design criteria for HTR
- Imprint Pagination
- 557 p.
- Journal Page Range
- p. 33-47.
- Report number
- Juel-Conf--71
Conference
- Title
- Workshop on structural design criteria for HTR.
- Dates
- 31 Jan - 1 Feb 1989.
- Place
- Juelich (Germany, F.R.).
INIS
- Country of Publication
- Germany
- Country of Input or Organization
- Germany
- INIS RN
- 21095063
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- HTGR TYPE REACTORS; HTTR REACTOR; JAPAN; PROCESS HEAT REACTORS; REACTOR COMPONENTS; REACTOR SAFETY
- Descriptors DEC
- ASIA; DEVELOPED COUNTRIES; ENRICHED URANIUM REACTORS; EXPERIMENTAL REACTORS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HELIUM COOLED REACTORS; POWER REACTORS; REACTORS; RESEARCH AND TEST REACTORS; SAFETY