Published October 1989 | Version v1
Report Open

The reactor core analysis code CITATION-1000VP for High Temperature Engineering Test Reactor

Creators

  • 1. Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

Description

Reactor core analysis with full core model has been necessary for the High Temperature Engineering Test Reactor (HTTR) design. The CITATION-1000VP code has been developed to enable reactor core analysis of HTTR with full core model through extending the number of zones and meshes, and enhancing the calculation speed of CITATION code. This report describes the program changes for extending the number of zones and meshes, and for vectorization. The maximum number of zones and meshes becomes 999 and 500, respectively. The calculation speed is enhanced up to 21 times. (author)

Availability note (English)

MF available from INIS under the Report Number.

Files

21032211.pdf

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Additional details

Publishing Information

Imprint Pagination
87 p.
Report number
JAERI-M--89-135

INIS

Country of Publication
Japan
Country of Input or Organization
Japan
INIS RN
21032211
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS; S99: GENERAL AND MISCELLANEOUS;
Descriptors DEI
C CODES; EFFICIENCY; FACOM COMPUTERS; HTTR REACTOR; MESH GENERATION; MULTIPLICATION FACTORS; NEUTRON FLUX; NEUTRON TRANSPORT; NUCLEAR ENGINEERING; POWER DENSITY; REACTOR CORES; REACTOR KINETICS; THREE-DIMENSIONAL CALCULATIONS; VECTOR PROCESSING
Descriptors DEC
COMPUTER CODES; COMPUTERS; ENGINEERING; ENRICHED URANIUM REACTORS; EXPERIMENTAL REACTORS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HELIUM COOLED REACTORS; HTGR TYPE REACTORS; KINETICS; NEUTRAL-PARTICLE TRANSPORT; PROGRAMMING; RADIATION FLUX; RADIATION TRANSPORT; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS