The MAAP code: What is it, what has it accomplished, and how can it be used in the future?

Journal Article · Tue Dec 31 00:00:00 EST 1996 · Transactions of the American Nuclear Society

OSTI ID:437025

Chao, J; Singh, A ^[1]; Henry, R; Plys, M; Paik, C ^[2]

---

1. Electric Power Research Inst., Palo Alto, CA (United States)
2. Fauske & Associates, Inc., Burr Ridge, IL (United States)

The Modular Accident Analysis Program (MAAP) represents a substantial effort by the nuclear industry to provide the analytical capabilities for analyzing the response of light-water-cooled nuclear power plants to possible accident conditions. This capability has also been developed for both current and advanced light water reactor designs and has been applied to the Ontario Hydro CANDU reactors as well as the VVER Russian pressurized water reactor (PWR) designs. The most recent version, i.e., MAAP4, substantially improves the representation of the primary system and containment and also adds a dynamic graphical representation of the plant response through the use of MAAP4-GRAAPH.

• OSTI ID: 437025
• Report Number(s): CONF-9606116-; ISSN 0003-018X; TRN: 96:005275-0264
• Journal Information: Transactions of the American Nuclear Society, Vol. 74; Conference: Annual meeting of the American Nuclear Society (ANS), Reno, NV (United States), 16-20 Jun 1996; Other Information: PBD: 1996
• Country of Publication: United States
• Language: English

Related Subjects

22 NUCLEAR REACTOR TECHNOLOGY
21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS
REACTOR ACCIDENTS
M CODES
REACTOR SAFETY
WATER COOLED REACTORS