On the natural convection cooling in HANARO (Hi-flux Advanced Neutron Application Reactor). Experiment and RELAP5/KMRR simulation
Creators
- 1. Korea Atomic Energy Research Inst., Taejon (Korea, Republic of). HANARO Center
Description
The natural circulation experiments were conducted to confirm the cooling capability and the flow characteristics of the natural convection in the HANARO (Hi-flux Advanced Neutron Application Reactor). The tests were done at the power levels of 2%, 3% and 4% (1.2MWth) of full power. The flow rates and temperatures at various locations of the primary and secondary cooling loops were measured at each power level. The temperature distributions in the chimney and the pool were also obtained. Through tests, the flow paths of the natural circulation and the cooling capability of the reactor were confirmed as designed. In addition, the simulation for the natural circulation tests was made by using RELAP5/KMRR, which was modified from RELAP5/MOD2 for applying to the HANARO conditions. The simulation results show that RELAP5/KMRR gives reasonable predictions for the flow rate and the coolant temperature during natural circulation condition in the HANARO. (author)
Additional details
Publishing Information
- Publisher
- Atomic Energy Society of Japan
- Imprint Place
- Tokyo (Japan)
- Imprint Title
- Eighth international topical meeting on nuclear reactor thermal-hydraulics
- Imprint Pagination
- 1890 p.
- Journal Page Range
- p. 1809-1814
Conference
- Title
- 8. international topical meeting on nuclear reactor thermal-hydraulics
- Acronym
- NURETH-8
- Dates
- 30 Sep - 4 Oct 1997
- Place
- Kyoto (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 30004399
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AFTER-HEAT REMOVAL; COMPUTERIZED SIMULATION; FLUID FLOW; HANARO REACTOR; MODIFICATIONS; NATURAL CONVECTION; PERFORMANCE; PRIMARY COOLANT CIRCUITS; R CODES; VALIDATION
- Descriptors DEC
- COMPUTER CODES; CONVECTION; COOLING SYSTEMS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; HEAT TRANSFER; IRRADIATION REACTORS; ISOTOPE PRODUCTION REACTORS; MATERIALS TESTING REACTORS; POOL TYPE REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; REMOVAL; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SIMULATION; TEST FACILITIES; TEST REACTORS; TESTING; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Imprint:Published in 3 volumes