RELAP4/MOD5: a computer program for transient thermal-hydraulic analysis of nuclear reactors and related systems. User's manual. Supplement 1, RELAP4/MOD5, Update 2. [BWR; PWR]

Technical Report · Sun Aug 01 00:00:00 EDT 1976

OSTI ID:7246806

Bruch, C G ^[1]

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1. ed.

RELAP4/MOD5, Update 1 was released to the Nuclear Regulatory Commission in January 1976. Six months of extensive use of Update 1 has led to the identification and correction of a number of errors in the code, as well as some logic changes, additional Evaluation Model (EM) checks, and one model revision. These changes have culminated in the release of an improved code identified as RELAP4/MOD5, Update 2. The RELAP4/MOD5 interim User's Manual (Interim Report SRD-113-76) reflected the Update 1 version of the code. The purpose of the supplement presented is to update the Interim User's Manual for use with RELAP4/MOD5, Update 2. Major differences between Updates 1 and 2 and the checkout of Update 2 are discussed. The final version of the User's Manual will be written in accordance with Update 2 and will be published as ANCR-NUREG 1335 during September 1976. Annotation of the existing three volumes of the User's Manual to cross-reference this Supplement is recommended.

• Research Organization: Idaho National Engineering Lab., Idaho Falls (USA)
• DOE Contract Number: E(10-1)-1375
• OSTI ID: 7246806
• Report Number(s): SRD-113-76(Suppl.1); TRN: 77-002138
• Country of Publication: United States
• Language: English

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LOSS OF COOLANT
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MATHEMATICAL MODELS
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COMPUTER CALCULATIONS
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