Source Term Code Package: a user's guide (Mod 1)
As part of a major reassessment of the release of radioactive materials to the environment (source terms) in severe reactor accidents, a group of state-of-the-art computer codes was utilized to perform extensive analyses. A major product of this source term reassessment effort was a demonstrated methodology for analyzing specific accident situations to provide source term predictions. The computer codes forming this methodology have been upgraded and modified for release and further use. This system of codes has been named the Source Term Code Package (STCP) and is the subject of this user's guide. The guide is intended to provide an understanding of the STCP structure and to facilitate STCP use. The STCP was prepared for operation on a CDC system but is written in FORTRAN-77 to permit transportability. In the current version (Mod 1) of the STCP, the various calculational elements fall into four major categories represented by the codes MARCH3, TRAP-MELT3, VANESA, and NAUA/SPARC/ICEDF. The MARCH3 code is a combination of the MARCH2, CORSOR-M, and CORCON-Mod 2 codes. The TRAP-MELT3 code is a combination of the TRAP-MELT2.0 and MERGE codes.
- Research Organization:
- Battelle Columbus Div., OH (USA)
- OSTI ID:
- 5593071
- Report Number(s):
- NUREG/CR-4587; BMI-2138; ON: TI86901596
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
FISSION PRODUCT RELEASE
ENVIRONMENTAL IMPACTS
M CODES
N CODES
T CODES
V CODES
MANUALS
RADIOACTIVE EFFLUENTS
CALCULATION METHODS
COMPUTERIZED SIMULATION
FORTRAN
COMPUTER CODES
DOCUMENT TYPES
MATERIALS
PROGRAMMING LANGUAGES
RADIOACTIVE MATERIALS
RADIOACTIVE WASTES
SIMULATION
WASTES
220900* - Nuclear Reactor Technology- Reactor Safety
220502 - Nuclear Reactor Technology- Environmental Aspects- Radioactive Effluents