PWR systems transient analysis: a reactor-safety perspective

Conference · Fri Jan 01 00:00:00 EST 1982

OSTI ID:6437837

Kennedy, M F; Abramson, P B; McDonald, T A

In the simulation of transient events in large PWR reactor systems for reactor safety studies, the plant model is quite detailed and must include most of the plant components and control systems to adequately analyze the range of transients. The results discussed were calculated with the RELAP4/MOD6 code and reveal the need for the analysis to carefully review and understand the results to assure that they are not being adversely affected by the improper solution techniques or changes in models during the calculation.

• Research Organization: Argonne National Lab., IL (USA)
• DOE Contract Number: W-31-109-ENG-38
• OSTI ID: 6437837
• Report Number(s): CONF-820810-17; ON: DE83008682
• Resource Relation: Conference: 10. international mathematics and computers simulation congress on systems simulation and scientific computation, Montreal, Canada, 9 Aug 1982
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
PWR TYPE REACTORS
TRANSIENTS
COMPUTER CALCULATIONS
REACTOR ACCIDENTS
SIMULATION
ACCIDENTS
REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled