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

研究成果: 書籍/レポート タイプへの寄稿会議への寄与

10 被引用数 (Scopus)

抄録

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.

本文言語英語
ホスト出版物のタイトルInternational Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015
出版社American Nuclear Society
ページ3030-3043
ページ数14
ISBN(電子版)9781510811843
出版ステータス出版済み - 2015
イベント16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2015 - Chicago, 米国
継続期間: 8月 30 20159月 4 2015

出版物シリーズ

名前International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015
4

その他

その他16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2015
国/地域米国
CityChicago
Period8/30/159/4/15

!!!All Science Journal Classification (ASJC) codes

  • 器械工学
  • 原子力エネルギーおよび原子力工学

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