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Posttest analysis of international standard problem 10 using RELAP4/MOD7. [PWR]

Year: 1981

Type: article

Abstract: RELAP4/MOD7, a best estimate computer code for the calculation of thermal and hydraulic phenomena in a nuclear reactor or related system, is the latest version in the RELAP4 code development series. This paper evaluates the capability of RELAP4/MOD7 to calculate refill/reflood phenomena. This evaluation uses the data of International Standard Problem 10, which is based on West Germany's KWU PKL refill/reflood experiment K9A. The PKL test facility represents a typical West German four-loop, 1300 MW pressurized water reactor (PWR) in reduced scale while maintaining prototypical volume-to-power ratio. The PKL facility was designed to specifically simulate the refill/reflood phase of a hypothetical loss-of-coolant accident (LOCA).

Source: University of North Texas Digital Library (University of North Texas)

Authors: Hsu, M., Davis, C.B., Peterson, A.C. Jr., Behling, S.R.

Language: English

Topic: Nuclear Engineering Thermal-Hydraulics

Subfield: Nuclear Energy and Engineering

Field: Energy

Domain: Physical Sciences

Open Access status: green

OpenAlex ID: W1503990552

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Related to: 10