Published March 1979 | Version v1
Report Open

Implementation of the thermal-hydraulic transient analysis code RELAP4/MOD5 and MOD6 on the FACOM 230/75 computer system

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

Description

Development efforts have continued on the extensively used LOCA analysis code RELAP-4, as seen in its history; that is, from the prototype version MOD2 to the latest one MOD6 which is capable of one-through calculations from blowdown to reflood phase of PWR-LOCA. Many improvements and refinements of the models have enlarged the scopes and extents of phenomena to treat. Correspondingly the size of program has increased version to version, and special programming techniques have continuously been introduced to manage the program within limited capacity of core memory. For example, the Dynamic Storage Allocation of MOD5 and the PRELOAD Preprocessor newly incorporated in MOD6 are those designed for the CDC computer with relatively small core size. Described are these programming techniques in detail and experiences on implementation of the codes on FACOM 230/75, together with some results of confirmatory calculations. (author)

Availability note (English)

MF available from INIS under the Report Number.

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Additional details

Publishing Information

Imprint Pagination
66 p.
Report number
JAERI-M--8166

INIS

Country of Publication
Japan
Country of Input or Organization
Japan
INIS RN
11503176
Subject category
S99: GENERAL AND MISCELLANEOUS;
Descriptors DEI
COMPUTER CALCULATIONS; FLOWSHEETS; LOSS OF COOLANT; M CODES; MANUALS; MEMORY DEVICES; R CODES; USES
Descriptors DEC
ACCIDENTS; COMPUTER CODES; DIAGRAMS; DOCUMENT TYPES; INFORMATION; REACTOR ACCIDENTS