Regional stability estimation of 1/3 MOX BWR-5 core with SIRIUS-F facility

Masahiro Furuya, Takanori Fukahori, Shinya Mizokami, Jun Yokoya

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

Abstract

The SIRIUS-F facility was designed and constructed for highly accurate simulation of channel instability, core-wide instability and regional instability of ABWR. A real-time simulation was performed by the modal-point kinetics of reactor neutronics and fuel-rod thermal conduction on the basis of a measured void fraction in a reactor core section of the facility. A noise analysis method was performed to calculate decay ratios and resonance frequencies from dominant poles of transfer function on the basis of the AR method using time series measurement data of a core inlet flow of the facility. By utilizing this method, one can estimate stability in any specific operating point online without assuming excess conservative conditions. Channel and regional stability experiments were conducted for a wide range of operating conditions including maximum power points along the minimum pump speed line and the natural circulation line of the BWR-5 core with one third of MOX fuels installed. The decay ratios and resonance frequencies are in good agreement with the analyses results calculated by design analysis code, ODYSY The SIRIUS-F experimental results demonstrated stability characteristics such as a stabilizing effect of the power, and revealed a sufficiently large stability margin even under hypothetical conditions of power level.

Original languageEnglish
Title of host publicationProceedings - 12th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH-12
Publication statusPublished - 2007 Dec 1
Externally publishedYes
Event12th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH-12 - Pittsburgh, PA, United States
Duration: 2007 Sep 302007 Oct 4

Publication series

NameProceedings - 12th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH-12

Conference

Conference12th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH-12
CountryUnited States
CityPittsburgh, PA
Period07/9/3007/10/4

Fingerprint

inlet flow
reactor cores
design analysis
Inlet flow
Reactor cores
Void fraction
decay
transfer functions
Transfer functions
voids
Time series
margins
Poles
poles
rods
simulation
reactors
Pumps
pumps
conduction

Keywords

  • BWR
  • Channel stability
  • Core-wide stability
  • Density wave oscillations
  • Regional stability

ASJC Scopus subject areas

  • Nuclear Energy and Engineering
  • Nuclear and High Energy Physics

Cite this

Furuya, M., Fukahori, T., Mizokami, S., & Yokoya, J. (2007). Regional stability estimation of 1/3 MOX BWR-5 core with SIRIUS-F facility. In Proceedings - 12th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH-12 (Proceedings - 12th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH-12).

Regional stability estimation of 1/3 MOX BWR-5 core with SIRIUS-F facility. / Furuya, Masahiro; Fukahori, Takanori; Mizokami, Shinya; Yokoya, Jun.

Proceedings - 12th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH-12. 2007. (Proceedings - 12th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH-12).

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

Furuya, M, Fukahori, T, Mizokami, S & Yokoya, J 2007, Regional stability estimation of 1/3 MOX BWR-5 core with SIRIUS-F facility. in Proceedings - 12th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH-12. Proceedings - 12th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH-12, 12th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH-12, Pittsburgh, PA, United States, 07/9/30.
Furuya M, Fukahori T, Mizokami S, Yokoya J. Regional stability estimation of 1/3 MOX BWR-5 core with SIRIUS-F facility. In Proceedings - 12th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH-12. 2007. (Proceedings - 12th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH-12).
Furuya, Masahiro ; Fukahori, Takanori ; Mizokami, Shinya ; Yokoya, Jun. / Regional stability estimation of 1/3 MOX BWR-5 core with SIRIUS-F facility. Proceedings - 12th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH-12. 2007. (Proceedings - 12th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH-12).
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