SIMMER-III. A coupled neutronics-thermohydraulics computer code for safety analysis
Creators
- 1. Japan Atomic Energy Agency, Oarai, Ibaraki (Japan)
- 2. Kyushu Univ., Fukuoka (JP)
- 3. Forschungszentrum Karlsruhe, Karlsruhe (DE)
- 4. Commissariat a l'Energie Atomique (FR)
Description
The SIMMER-III code is a two-dimensional, multi-velocity-field, multi-phase, multi-component, Eulerian, fluid-dynamics code coupled with a fuel-pin model and a space- and energy-dependent neutron transport kinetics model. Since SIMMER-III is expected to become a standard tool for fast reactor safety analysis with likely application to licensing calculations, the code must be demonstrated to be sufficiently robust and reliable. For this purpose, a systematic assessment program of the code has been conducted in cooperation with European partners. The philosophy behind the code development was to generate a versatile and flexible tool, thus SIMMER-III has been applied to safety analyses of various reactor types with different neutron spectra and coolants. Since the three-dimensional representation of the core enables realistic distribution of the materials constituting the core including control rods, the development of SIMMER-IV has been performed to be a direct extension of SIMMER-III to three dimensions with retaining exactly the same physical models as SIMMER-III. Recently, the parallelization of SIMMER-IV has been made to allow applications to reactor calculation within available computational resource. A three-dimensional calculation with SIMMER-IV is presented to indicate more realistic accident scenario. (author)
Availability note (English)
Available from Japan Society of Mechanical Engineers, 35 Shinanomachi, Shinjuku-ku, Tokyo 160-0016, JapanAdditional details
Publishing Information
- Publisher
- Japan Society of Mechanical Engineers
- Imprint Place
- Tokyo (Japan)
- Imprint Title
- Proceedings of the ICONE-15 (Revised). The 15th international conference on nuclear engineering
- Imprint Pagination
- [3174 p.]
- Journal Page Range
- [8 p.]
Conference
- Title
- 15. international conference on nuclear engineering
- Acronym
- ICONE-15
- Dates
- 22-26 Apr 2007
- Place
- Nagoya, Aichi (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 39087298
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTERIZED SIMULATION; FAST REACTORS; FLUID MECHANICS; MULTIPHASE FLOW; NEUTRON SPECTRA; NEUTRON TRANSPORT; PARALLEL PROCESSING; REACTOR CORE DISRUPTION; S CODES; SAFETY ANALYSIS; SODIUM COOLED REACTORS; TWO-DIMENSIONAL CALCULATIONS; VALIDATION
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; EPITHERMAL REACTORS; FLUID FLOW; LIQUID METAL COOLED REACTORS; MECHANICS; NEUTRAL-PARTICLE TRANSPORT; PROGRAMMING; RADIATION TRANSPORT; REACTOR ACCIDENTS; REACTORS; SIMULATION; SPECTRA; TESTING
Optional Information
- Notes
- This CD-ROM can be used for WINDOWS 9x/NT/2000/ME/XP, MACINTOSH; Acrobat Reader is included; Data in PDF format, Folder Name Final Paper, PaperID ICONE15-10462.pdf; 35 refs., 12 figs.