Validation of Heat Transfer Models in Narrow Gap for RELAP/SCDAPSIM/MOD3.2

Kohriyama, Tamio; Murase, Michio; Nagae, Takashi; Okano, Yukimitsu; Ezzidi, A.

doi:10.13182/nt04-a3525

Cited by 4 publications

(1 citation statement)

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“…In addition to the modelling 1 2 3 2 3 29 30 79 179 1171 1071 71 71 71 71 71 71 1 2 3 2 3 29 30 174 174 174 174 174 174 improvements driven by large-scale experimental programs in the Phebus and Quench facilities as discussed in the previous section, other model and code development activities have been driven by the needs of SDTP members and licensed software users. INSS (Institute of Nuclear Safety System), Japan, one of the original members of SDTP, developed and validated new RELAP/SCDAPSIM models to treat the heat transfer in the gap between a debris bed and the lower plenum wall [38] and improved correlations for condensation in the presence of noncondensable gases [39]. The applications of the improved correlations are described in [40].…”

Section: Development Of Improved Models and Analytic Capabilitiesmentioning

confidence: 99%

Role of RELAP/SCDAPSIM in Nuclear Safety

Allison¹,

Hohorst²

2010

Science and Technology of Nuclear Installations

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The RELAP/SCDAPSIM code, designed to predict the behaviour of reactor systems during normal and accident conditions, is being developed as part of the international SCDAP Development and Training Program (SDTP). SDTP consists of nearly 60 organizations in 28 countries supporting the development of technology, software, and training materials for the nuclear industry. The program members and licensed software users include universities, research organizations, regulatory organizations, vendors, and utilities located in Europe, Asia, Latin America, and the United States. Innovative Systems Software (ISS) is the administrator for the program. RELAP/SCDAPSIM is used by program members and licensed users to support a variety of activities. The paper provides a brief review of some of the more important activities including the analysis of research reactors and Nuclear Power Plants, design and analysis of experiments, and training.

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Section: Development Of Improved Models and Analytic Capabilitiesmentioning

confidence: 99%