Published 1991
| Version v1
Book
In-core fuel management: PWR core calculations using MCRAC
Description
In-core fuel management involves repetitive, numerous spatial core calculations, which raises a need for appropriate computational tools. This lecture notes describe Multicycle Reactor Analysis Code (MCRAC), which is a two-dimensional two-group diffusion code that may be used for such calculations. Emphasis is placed on practical aspects of applying MCRAC to pressurized water reactor in-core fuel management calculations; various code features and options are discussed and clarified. 19 refs, 13 figs, 8 tabs
Additional details
Publishing Information
- Publisher
- World Scientific.
- Imprint Place
- Singapore (Singapore)
- ISBN
- 981-02-0517-1
- Imprint Title
- Workshop on reactor physics calculations for applications in nuclear technology
- Imprint Pagination
- 752 p.
- Journal Page Range
- p. 360-397.
Conference
- Title
- Workshop on reactor physics calculations for applications in nuclear technology.
- Dates
- 12 Feb - 16 Mar 1990.
- Place
- Trieste (Italy).
INIS
- Country of Publication
- Singapore
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 23059635
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BURNUP; COMPUTER CALCULATIONS; FUEL MANAGEMENT; M CODES; PWR TYPE REACTORS; REACTOR CELLS; TWO-DIMENSIONAL CALCULATIONS
- Descriptors DEC
- COMPUTER CODES; ENRICHED URANIUM REACTORS; MANAGEMENT; NUCLEAR MATERIALS MANAGEMENT; POWER REACTORS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS