PARTITION: A program for defining the source term/consequence analysis interface in the NUREG--1150 probabilistic risk assessments

Technical Report · Tue May 01 00:00:00 EDT 1990

DOI:https://doi.org/10.2172/6980332· OSTI ID:6980332

Iman, R L ^[1]; Helton, J C ^[2]; Johnson, J D ^[3]

---

1. Sandia National Labs., Albuquerque, NM (USA)
2. Arizona State Univ., Tempe, AZ (USA)
3. Science Applications International Corp., Albuquerque, NM (USA)

The individual plant analyses in the US Nuclear Regulatory Commission's reassessment of the risk from commercial nuclear power plants (NUREG-1150) consist of four parts: systems analysis, accident progression analysis, source term analysis, and consequence analysis. Careful definition of the interfaces between these parts is necessary for both information flow and computational efficiency. This document has been designed for users of the PARTITION computer program developed by the authors at Sandia National Laboratories for defining the interface between the source term analysis (performed with the XXSOR programs) and the consequence analysis (performed with the MACCS program). This report provides a tutorial that details how the interactive partitioning is performed, along with detailed information on the partitioning process. The PARTITION program was written in ANSI standard FORTRAN 77 to make the code as machine-independent (i.e., portable) as possible. 9 refs., 4 figs.

• Research Organization: Nuclear Regulatory Commission, Washington, DC (USA). Div. of Systems Research; Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)
• Sponsoring Organization: USNRC
• DOE Contract Number: AC04-76DP00789
• OSTI ID: 6980332
• Report Number(s): NUREG/CR-5253; SAND-88-2940; ON: TI90011475; TRN: 90-017815
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE
NUCLEAR POWER PLANTS
RISK ASSESSMENT
P CODES
SOURCE TERMS
COMPUTER CODES
DOCUMENTATION
FORTRAN
HEALTH HAZARDS
M CODES
REACTOR ACCIDENTS
ACCIDENTS
HAZARDS
NUCLEAR FACILITIES
POWER PLANTS
PROGRAMMING LANGUAGES
THERMAL POWER PLANTS
220900* - Nuclear Reactor Technology- Reactor Safety
220502 - Nuclear Reactor Technology- Environmental Aspects- Radioactive Effluents
990200 - Mathematics & Computers