Generic Containment: A Detailed Comparison of Containment Simulations performed on Plant Scale

St. Kelm, Ph. Broxtermann, S. Krajewski, Ari Silde, et al.

Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientificpeer-review

Abstract

One outcome of the OECD/NEA ISP-47 (TOSQAN, MISTRA, THAI) activity was the recommendation to elaborate a 'Generic Containment' including all important components. On the one hand, this Generic Containment helps to rate analyses being performed with different lumped-parameter models. On the other hand, it serves as a basis for testing new model developments on a commonly available and accepted basis. Within the SARNET2 Network of Excellence, such a Generic Containment nodalisation, based on a German PWR (1300 MWel), has been developed and is applied for a lumped parameter code-to-code comparison with systematically increasing complexity. Within the second step of the benchmark exercise, run1, a detailed evaluation is performed in order to achieve an understanding of the basic differences among the codes and models and the resulting deviations. The paper discusses the general methodology and its application in the detailed evaluation of run1
Original languageEnglish
Title of host publicationProceedings of 15th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-15)
Number of pages18
EditionUSB flash drive
Publication statusPublished - 2013
MoE publication typeA4 Article in a conference publication
Event15th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH-15 - Pisa, Italy
Duration: 12 May 201315 May 2013

Conference

Conference15th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH-15
Abbreviated titleNURETH-15
CountryItaly
CityPisa
Period12/05/1315/05/13

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    Kelm, S., Broxtermann, P., Krajewski, S., Silde, A., & et al. (2013). Generic Containment: A Detailed Comparison of Containment Simulations performed on Plant Scale. In Proceedings of 15th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-15) (USB flash drive ed.)