High-temperature gas cooled reactor HTTR reaching the first critical point
Creators
- 1. Japan Atomic Energy Research Inst., Oarai, Ibaraki (Japan). Oarai Research Establishment
Description
Outline, fueling, conditions of criticality test, and future plan of HTTR (high-temperature test reactor) of Japan Atomic Energy Research Institute are described. HTTR is the world first nuclear reactor that can directly take out high-temperature helium gas of 850-950degC outside the reactor pressure vessel, and aims at establishment and upgrading of high-temperature gas cooled reactor technological basis and frontier basic research of high-temperature engineering, and started the construction in March 1991 and reached the first critical point on November 10, 1998. The basic specifications are: Output: 30 MW; primary coolant: helium; core material: graphite; core height: 2.9 m; core diameter: 2.3 m; fuel: uranium dioxide coated particle/graphite dispersion-type; uranium enrichment: 3-10% (average 6%). The enrichment can be adjusted by site so that temperatures of the helium flowing out are uniformly distributed. The critical point was reached with 19 fuel columns filled out of full 30 columns and with 16 pairs of control rods all drawn out except the central control rod, which was gradually drawn out to about 60% of the stroke. Then, fueling proceeded to the full 30 columns through 21, 24 and 27 for further nuclear characteristic tests. The full output is planned to reach in a year from the start of the output increasing test in September 1999. (M.M.)
Additional details
Publishing Information
- Journal Title
- Genshiryoku eye
- Journal Volume
- 45
- Journal Issue
- 4
- Journal Page Range
- p. 60-63
- ISSN
- 1343-3563
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 30032901
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- COMPARATIVE EVALUATIONS; CRITICALITY; HTTR REACTOR; JAERI; REACTOR CORES; REACTOR FUELING; RESEARCH PROGRAMS
- Descriptors DEC
- ENRICHED URANIUM REACTORS; EVALUATION; EXPERIMENTAL REACTORS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HELIUM COOLED REACTORS; HTGR TYPE REACTORS; JAPANESE ORGANIZATIONS; NATIONAL ORGANIZATIONS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS