Reactivity initiated accident analyses for the safety assessment of JRR-2 MEU core
Creators
- 1. Japan Atomic Energy Research Inst., Tokai, Ibaraki. Tokai Research Establishment
Description
JRR-2 is a 10 MW research reactor moderated and cooled with heavy water. The JRR-2 core is currently planed to be converted from highly-enriched uranium (HEU:93 %) core to medium-enriched uranium (MEU:45 %) core. This report describes the analytical results of reactivity initiated accidents for the safety assessment of JRR-2 MEU Core. The following four cases have been selected for the assessment; (1) uncontrolled control rod withdrawal from zero power, (2) uncontrolled control rod withdrawal from full power, (3) removal of irradiation samples, (4) drop of primaly coolant temperature. Parameter studies have been made for each of the above cases. All analyses have been made by a computer code EUREKA-2. The results show that the safety criteria for JRR-2 MEU core are all met. (author)
Availability note (English)
MF available from INIS under the Report Number.Files
18100199.pdf
Files
(1.4 MB)
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Additional details
Publishing Information
- Imprint Pagination
- 47 p.
- Report number
- JAERI-M--87-074
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 18100199
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- CONTROL ELEMENTS; E CODES; HEAVY WATER; JRR-2 REACTOR; REACTIVITY; REACTIVITY INSERTIONS; REACTOR SAFETY; SAFETY ANALYSIS; TEMPERATURE DEPENDENCE; TRANSIENTS
- Descriptors DEC
- COMPUTER CODES; ENRICHED URANIUM REACTORS; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; HYDROGEN COMPOUNDS; OXYGEN COMPOUNDS; POLAR SOLVENTS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SAFETY; SOLVENTS; TANK TYPE REACTORS; WATER