Published 1988 | Version v1
Book

Physical modelling of the in-vessel phases of severe reactor accidents: The MELPROG/TRAC computer code

  • 1. Sandia Natinal Labs., Albuquerque, NM (USA). Reactor Safety Theoretical Physics Div.
  • 2. Los Alamos National Lab., NM (USA). Safety Code Development Group

Description

The MELPROG/TRAC computer code is the U.S.N.R.C. best-estimate model for analysis of phenomena in the reactor vessel and reactor coolant system associated with the progression of severe accidents in light water reactors. Although versions exist for both boiling water reactors and pressurized water reactors, the discussion is confined to the pressurized water reactor. The structure of MELPROG/TRAC is briefly summarized, its capabilities outlined, and results from typical analyses noted. As a specific example, differences in the initiation phase of a station blackout accident caused by pump seal failures are described. Finally, experimental and analytical efforts to assess the modelling basis for MELPROG/TRAC are outlined. (author). 14 refs, 4 figs

Part of:
Severe accidents in nuclear power plants. V.2

Additional details

Publishing Information

Publisher
IAEA.
Imprint Place
Vienna (Austria)
ISBN
92-0-020288-8
Imprint Title
Severe accidents in nuclear power plants
Imprint Pagination
772 p.
Series
Proceedings series.
Journal Page Range
v. 2 p. 165-178.

Conference

Title
International symposium on severe accidents in nuclear power plants.
Dates
21-25 Mar 1988.
Place
Sorrento (Italy).

INIS

Country of Publication
Austria
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
20034870
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
FAILURES; FISSION PRODUCT RELEASE; HYDROGEN; M CODES; MELTDOWN; MOLTEN METAL-WATER REACTIONS; PRESSURE VESSELS; PWR TYPE REACTORS; TIME DEPENDENCE
Descriptors DEC
ACCIDENTS; COMPUTER CODES; CONTAINERS; ELEMENTS; ENRICHED URANIUM REACTORS; NONMETALS; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Contract/Grant/Project number
Contract DE-AC04-76DP00789
Secondary number(s)
IAEA-SM--296/97.