MITR RELAP5 Model Validations at Steady States and Transients
- 1. Nuclear Reactor Laboratory, Massachusetts Institute of Technology, Cambridge, MA, 20139, USA (United States)
- 2. Department of Nuclear Science and Technology, Xi'an Jiaotong University, Xi'an 710049, China (China)
- 3. Institute of Nuclear Engineering and Science, National Tsing Hua University, Hsinchu, 30013, Taiwan (China)
Description
The Massachusetts Institute of Technology Reactor (MITR-II) is a 6 MW university research reactor designed primarily for experiments using neuron beams and in-core irradiation facilities, and education. The objective of this study is to validate the MITR RELAP5 model, which includes the reactor core, primary coolant loop, secondary coolant loop and heat exchanger models. Two sets of operational data were collected for validation. Steady-state data for 1 MW, 3 MW, 5.5 MW was obtained in the first test. The continuous startup transient data and the cooling tower outlet coolant temperature reduction obtained during the second test. The five steady-state conditions and two transient conditions were calculated by the RELAP5. The reactor power and cooling tower outlet temperature were used as boundary conditions while the reactor core inlet temperature and outlet temperature were calculated. A comparison was made between the modeling results and the temperature measurements. The results show that the MITR RELAP5 modeling results are in good agreement with measurement data for both steady-state and transient conditions
Additional details
Publishing Information
- Journal Title
- Transactions of the American Nuclear Society
- Journal Volume
- 116
- Journal Page Range
- p. 1393-1396
- ISSN
- 0003-018X
Conference
- Title
- 2017 Annual Meeting of the American Nuclear Society
- Dates
- 11-15 Jun 2017
- Place
- San Francisco, CA (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 52090786
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S42: ENGINEERING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BOUNDARY CONDITIONS; COMPUTERIZED SIMULATION; HEAT EXCHANGERS; IRRADIATION PLANTS; PRIMARY COOLANT CIRCUITS; REACTOR CORES; REACTOR DESIGN; RESEARCH REACTORS; SECONDARY COOLANT CIRCUITS; STEADY-STATE CONDITIONS; TEMPERATURE MEASUREMENT; TRANSIENTS; VALIDATION
- Descriptors DEC
- COOLING SYSTEMS; DESIGN; ENERGY SYSTEMS; NUCLEAR FACILITIES; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTOR LIFE CYCLE; REACTORS; RESEARCH AND TEST REACTORS; SIMULATION; TESTING
Optional Information
- Notes
- 6 refs.; available from American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 (US)