Implementation of the thermal-hydraulic transient analysis code RELAP4/MOD5 and MOD6 on the FACOM 230/75 computer system
Creators
- 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.Files
11503176.pdf
Files
(2.0 MB)
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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