Published 2007 | Version v1
Computer medium

SIMMER-III. A coupled neutronics-thermohydraulics computer code for safety analysis

  • 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, Japan
Part of:
Proceedings of the ICONE-15 (Revised). The 15th international conference on nuclear engineering

Additional 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)

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.