EBR-II passive safety demonstration tests benchmark analyses-phase 2

L. Briggs, W. Hu, G. H. Su, B. Vezzoni, A. Del Nevo, S. Monti, D. Sui, L. Maas, U. Partha Sarathy, A. Petruzzi, R. Zanino, H. Ohira, H. Mochizuki, K. Morita, C. Choi, A. Shin, M. Stempniewicz, N. Rtishchev, Y. Zhang, B. Truong

Research output: Chapter in Book/Report/Conference proceedingConference contribution

4 Citations (Scopus)

Abstract

The International Atomic Energy Agency Coordinated Research Project, "Benchmark Analyses of an EBR-II Shutdown Heat Removal Test" is in the third year of its four-year term. Nineteen participants representing eleven countries have simulated two of the most severe transients performed during the Shutdown Heat Removal Tests program conducted at Argonne's Experimental Breeder Reactor II. Benchmark specifications were created for these two transients, enabling project participants to develop computer models of the core and primary heat transport system, and simulate both transients. In phase 1 of the project, blind simulations were performed and then evaluated against recorded data. During phase 2, participants have refined their models to address areas where the phase 1 simulations did not predict the experimental data as well as desired. This paper describes the progress that has been made to date in phase 2 in improving on the earlier simulations and presents the direction of planned work for the remainder of the project.

Original languageEnglish
Title of host publicationInternational Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015
PublisherAmerican Nuclear Society
Pages3030-3043
Number of pages14
ISBN (Electronic)9781510811843
Publication statusPublished - Jan 1 2015
Event16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2015 - Chicago, United States
Duration: Aug 30 2015Sep 4 2015

Publication series

NameInternational Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015
Volume4

Other

Other16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2015
CountryUnited States
CityChicago
Period8/30/159/4/15

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All Science Journal Classification (ASJC) codes

  • Instrumentation
  • Nuclear Energy and Engineering

Cite this

Briggs, L., Hu, W., Su, G. H., Vezzoni, B., Del Nevo, A., Monti, S., ... Truong, B. (2015). EBR-II passive safety demonstration tests benchmark analyses-phase 2. In International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015 (pp. 3030-3043). (International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015; Vol. 4). American Nuclear Society.