Published November 2000 | Version v1
Report Metadata-only

SIMMER-IV: A three-dimensional computer program for LMFR core disruptive accident analysis. Version 1.B model summary and program description

Creators

  • 1. Japan Nuclear Cycle Development Inst., Oarai, Ibaraki (Japan). Oarai Engineering Center
  • 2. Nuclear Energy Systems, Inc., Tokyo (Japan)

Description

An advanced safety analysis computer code, SIMMER-III, has been developed at Japan Nuclear Cycle Development Institute (JNC) to more realistically investigate postulated core disruptive accidents in liquid-metal fast reactors. The two-dimensional framework of SIMMER-III fluid dynamics has been extended to three dimensions to a new code, SIMMER-IV, which is currently (in Version 1) coupled with the existing two-dimensional neutronics model. With the completion of the first SIMMER-IV version, the applicability of the code is further enhanced and the many of the known limitations in SIMMER-III are eliminated. The sample calculations demonstrated the general validity of SIMMER-IV. This report describes SIMMER-IV Version 1.B, by documenting the models, numerical algorithms and code features, along with the program description and input and output information to aid the users. Further extension of the code is planned to couple the three-dimensional neutronics in the future. (author)

Availability note (English)

Available from JICST Library (JICST: Japan Science and Technology Corporation, Information Center for Science and Technology), P.O. Box 10 Hikarigaoka, Tokyo 179-9810 Japan, FAX: +81-3-3979-4781, JICST Service Homepage: www.jst.go.jp/EN/

Additional details

Publishing Information

Imprint Pagination
307 p.
Report number
JNC-TN--9400-2001-003

INIS

Country of Publication
Japan
Country of Input or Organization
Japan
INIS RN
33004689
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Non-conventional Literature
Descriptors DEI
ALGORITHMS; ANALYTICAL SOLUTION; LMFBR TYPE REACTORS; MODIFICATIONS; PROGRAMMING; REACTOR CORE DISRUPTION; RELIABILITY; S CODES; SAFETY ANALYSIS; THREE-DIMENSIONAL CALCULATIONS
Descriptors DEC
ACCIDENTS; BREEDER REACTORS; COMPUTER CODES; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; LIQUID METAL COOLED REACTORS; MATHEMATICAL LOGIC; REACTOR ACCIDENTS; REACTORS

Optional Information

Notes
23 refs., 17 figs., 9 tabs.