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

Fingerprint

safety
shutdowns
Demonstrations
heat
breeder reactors
Breeder reactors
simulation
research projects
nuclear energy
Nuclear energy
specifications
Specifications
Hot Temperature

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.

EBR-II passive safety demonstration tests benchmark analyses-phase 2. / Briggs, L.; Hu, W.; Su, G. H.; Vezzoni, B.; Del Nevo, A.; Monti, S.; Sui, D.; Maas, L.; Sarathy, U. Partha; Petruzzi, A.; Zanino, R.; Ohira, H.; Mochizuki, H.; Morita, K.; Choi, C.; Shin, A.; Stempniewicz, M.; Rtishchev, N.; Zhang, Y.; Truong, B.

International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015. American Nuclear Society, 2015. p. 3030-3043 (International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015; Vol. 4).

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

Briggs, L, Hu, W, Su, GH, Vezzoni, B, Del Nevo, A, Monti, S, Sui, D, Maas, L, Sarathy, UP, Petruzzi, A, Zanino, R, Ohira, H, Mochizuki, H, Morita, K, Choi, C, Shin, A, Stempniewicz, M, Rtishchev, N, Zhang, Y & 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. International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015, vol. 4, American Nuclear Society, pp. 3030-3043, 16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2015, Chicago, United States, 8/30/15.
Briggs L, Hu W, Su GH, Vezzoni B, Del Nevo A, Monti S et al. EBR-II passive safety demonstration tests benchmark analyses-phase 2. In International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015. American Nuclear Society. 2015. p. 3030-3043. (International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015).
Briggs, L. ; Hu, W. ; Su, G. H. ; Vezzoni, B. ; Del Nevo, A. ; Monti, S. ; Sui, D. ; Maas, L. ; Sarathy, U. Partha ; Petruzzi, A. ; Zanino, R. ; Ohira, H. ; Mochizuki, H. ; Morita, K. ; Choi, C. ; Shin, A. ; Stempniewicz, M. ; Rtishchev, N. ; Zhang, Y. ; Truong, B. / EBR-II passive safety demonstration tests benchmark analyses-phase 2. International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015. American Nuclear Society, 2015. pp. 3030-3043 (International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015).
@inproceedings{2cc878f2cd2444c1b67163a09933fb0d,
title = "EBR-II passive safety demonstration tests benchmark analyses-phase 2",
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.",
author = "L. Briggs and W. Hu and Su, {G. H.} and B. Vezzoni and {Del Nevo}, A. and S. Monti and D. Sui and L. Maas and Sarathy, {U. Partha} and A. Petruzzi and R. Zanino and H. Ohira and H. Mochizuki and K. Morita and C. Choi and A. Shin and M. Stempniewicz and N. Rtishchev and Y. Zhang and B. Truong",
year = "2015",
month = "1",
day = "1",
language = "English",
series = "International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015",
publisher = "American Nuclear Society",
pages = "3030--3043",
booktitle = "International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015",
address = "United States",

}

TY - GEN

T1 - EBR-II passive safety demonstration tests benchmark analyses-phase 2

AU - Briggs, L.

AU - Hu, W.

AU - Su, G. H.

AU - Vezzoni, B.

AU - Del Nevo, A.

AU - Monti, S.

AU - Sui, D.

AU - Maas, L.

AU - Sarathy, U. Partha

AU - Petruzzi, A.

AU - Zanino, R.

AU - Ohira, H.

AU - Mochizuki, H.

AU - Morita, K.

AU - Choi, C.

AU - Shin, A.

AU - Stempniewicz, M.

AU - Rtishchev, N.

AU - Zhang, Y.

AU - Truong, B.

PY - 2015/1/1

Y1 - 2015/1/1

N2 - 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.

AB - 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.

UR - http://www.scopus.com/inward/record.url?scp=84962738523&partnerID=8YFLogxK

UR - http://www.scopus.com/inward/citedby.url?scp=84962738523&partnerID=8YFLogxK

M3 - Conference contribution

AN - SCOPUS:84962738523

T3 - International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015

SP - 3030

EP - 3043

BT - International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015

PB - American Nuclear Society

ER -