Development of MARCH 2
Description
The MARCH code has been widely used for describing the wide variety of physical processes associated with core meltdown accidents. The efforts associated with the development of MARCH 2, a revised version of the reference code, are described. These include changes in the code structure as well as improvements in the phenomenological models. The changes in code structure are designed to improve the flexibility for the treatment of a variety of accident sequences and facilitate the transportability of the code. The principal changes in phenomenological modeling are related to updated decay heating correlations, improved primary system blowdown for transients and small breaks, more detailed treatment of in-core heat transfer processes, extended modeling of metal-water reactions, more mechanistic treatment of core debris interaction with water, and improvements in the treatment of the burning of hydrogen and other combustibles. Results of comparisons between MARCH 2 predictions and those of MARCH 1.1 are presented
Additional details
Additional titles
- Augmented title (English)
- PWR; BWR
Publishing Information
- Imprint Title
- Proceedings of the international meeting on thermal nuclear reactor safety. Vol. 2
- Journal Page Range
- p. 1158-1166.
- Report number
- NUREG/CP--0027-Vol.2
Conference
- Title
- International meeting on thermal nuclear reactor safety (ANS topical meeting).
- Dates
- 29 Aug - 2 Sep 1982.
- Place
- Chicago, IL (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 14792426
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BWR TYPE REACTORS; COMPUTER CALCULATIONS; HEAT TRANSFER; HYDRAULICS; M CODES; MELTDOWN; PRESSURE GRADIENTS; PWR TYPE REACTORS; REACTOR SAFETY; SPATIAL DISTRIBUTION; TEMPERATURE DISTRIBUTION
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; DISTRIBUTION; ENERGY TRANSFER; REACTOR ACCIDENTS; REACTORS; SAFETY; WATER COOLED REACTORS; WATER MODERATED REACTORS