Trace/simulate-3k analysis of the NEA/OECD oskarshamn-2 stability benchmark

Abdelhamid Dokhane, Omar Zerkak, Hakim Ferroukhi, Ivan Gajev, Jerry Judd, Tomasz Kozlowski

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

Abstract

A coupling between TRACE and SIMULATE-3K (TS3K) was developed in collaboration between PSI and Studsvik for analyses involving interactions between system and core, with the goal to enhance the capability to perform best-estimate simulations of Light Water Reactors (LWRs) transients, with strong coupling between core neutronics and plant thermal-hydraulic. In order to verify the coupling scheme and the coupled code capabilities to simulate complex transients, the OECD/NEA Oskarshmn-2 (0-2) Stability benchmark, launched recently, was modeled with the coupled code TS3K. The main goal of this paper is to present TS3K analyses of the Oskarshamn-2 stability event, noting that this constitutes the first reported assessment of this code system for a BWR stability problem. A systematic analysis is carried out using different time-space discretization schemes in order to identify an optimized methodology to simulate correctly the 0-2 stability event. In this context the TS3K results are compared to the available benchmark data both for steady-state and transient conditions. The results show that using a refined model in space and time, the TS3K model can successfully capture the entire behavior of the transient qualitatively, i.e. onset of the instability with growing oscillation amplitudes, as well as quantitatively, i.e. Decay Ratio and resonance frequency. However, it is also shown that the qualitative as well as quantitative trends predicted by TS3K during the transient phase, especially when power oscillations start to take place, is highly sensitive to the pump boundary conditions and that the benchmark specification might in this context need to be further reviewed.

Original languageEnglish (US)
Title of host publicationInternational Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015
PublisherAmerican Nuclear Society
Pages4757-4770
Number of pages14
ISBN (Electronic)9781510811843
StatePublished - 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
Volume6

Other

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

Fingerprint

light water reactors
oscillations
Light water reactors
hydraulics
specifications
Hydraulics
Boundary conditions
Pumps
methodology
pumps
boundary conditions
Specifications
trends
decay
estimates
simulation
interactions
Hot Temperature

Keywords

  • Coupling
  • Oskarshamn-2
  • SIMULATE-3K. TRACE
  • Stability of BWR

ASJC Scopus subject areas

  • Instrumentation
  • Nuclear Energy and Engineering

Cite this

Dokhane, A., Zerkak, O., Ferroukhi, H., Gajev, I., Judd, J., & Kozlowski, T. (2015). Trace/simulate-3k analysis of the NEA/OECD oskarshamn-2 stability benchmark. In International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015 (pp. 4757-4770). (International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015; Vol. 6). American Nuclear Society.

Trace/simulate-3k analysis of the NEA/OECD oskarshamn-2 stability benchmark. / Dokhane, Abdelhamid; Zerkak, Omar; Ferroukhi, Hakim; Gajev, Ivan; Judd, Jerry; Kozlowski, Tomasz.

International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015. American Nuclear Society, 2015. p. 4757-4770 (International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015; Vol. 6).

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

Dokhane, A, Zerkak, O, Ferroukhi, H, Gajev, I, Judd, J & Kozlowski, T 2015, Trace/simulate-3k analysis of the NEA/OECD oskarshamn-2 stability benchmark. in International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015. International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015, vol. 6, American Nuclear Society, pp. 4757-4770, 16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2015, Chicago, United States, 8/30/15.
Dokhane A, Zerkak O, Ferroukhi H, Gajev I, Judd J, Kozlowski T. Trace/simulate-3k analysis of the NEA/OECD oskarshamn-2 stability benchmark. In International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015. American Nuclear Society. 2015. p. 4757-4770. (International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015).
Dokhane, Abdelhamid ; Zerkak, Omar ; Ferroukhi, Hakim ; Gajev, Ivan ; Judd, Jerry ; Kozlowski, Tomasz. / Trace/simulate-3k analysis of the NEA/OECD oskarshamn-2 stability benchmark. International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015. American Nuclear Society, 2015. pp. 4757-4770 (International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015).
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