Published November 1990 | Version v1
Report Metadata-only

CORD - a programme package for PWR core design calculations

Creators

  • 1. Institut Jozef Stefan, Ljubljana (Yugoslavia)

Description

Functional description of the programme package CORD for PWR core design calculations is presented. Main programmes are described and plans for upgrading are discussed. Use of the package and calculational procedures for typical core design problems are treated. Comparison of main results with experimental values is presented as part of qualification process. Practical problems concerning quality control of calculations and final results are discussed. (author). 5 refs, 2 figs, 3 tabs

Part of:
In-core fuel management practices. Proceedings of two technical committee meetings and workshops held in Madrid, 12-15 July 1988, and Vienna, 4-7 December 1989

Additional details

Publishing Information

Imprint Title
In-core fuel management practices. Proceedings of two technical committee meetings and workshops held in Madrid, 12-15 July 1988, and Vienna, 4-7 December 1989
Imprint Pagination
438 p.
Journal Page Range
p. 115-119.
Report number
IAEA-TECDOC--567

Conference

Title
Technical committee meeting and workshop on improvements of in-core fuel management codes.
Dates
12-15 Jul 1988.
Place
Madrid (Spain).

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
22023359
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
C CODES; FUEL MANAGEMENT; PWR TYPE REACTORS; REACTOR CORES; SPECIFICATIONS; VERIFICATION
Descriptors DEC
COMPUTER CODES; ENRICHED URANIUM REACTORS; MANAGEMENT; NUCLEAR MATERIALS MANAGEMENT; POWER REACTORS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information