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Multiphase Science and Technology
SJR: 0.183 SNIP: 0.483 CiteScore™: 0.5

ISSN Imprimir: 0276-1459
ISSN En Línea: 1943-6181

Multiphase Science and Technology

DOI: 10.1615/MultScienTechn.v18.i4.20
pages 335-358

EXPERIMENTAL STUDY ON STABILITY OF STARTUP IN NATURAL CIRCULATION BWRS WITH AND WITHOUT NUCLEAR COUPLING

Mamoru Ishii
Therma-Hydraulics and Reactor Safety Laboratory, School of Nuclear Engineering, Purdue University, 400 Central Drive, West Lafayette, IN 47907, USA
Selim Kuran
Global Nuclear Fuel - Americas
Xiaodong Sun
Nuclear Engineering Program, Department of Mechanical and Aerospace Engineering, The Ohio State University, 201 W 19th Avenue, Columbus, OH 43210, USA
Ling Cheng
Thermal-Hydraulics and Reactor Safety Laboratory, School of Nuclear Engineering, Purdue University, 400 Central Drive, West Lafayette, IN 47907, USA
Yiban Xu
Thermal-Hydraulics and Reactor Safety Laboratory, School of Nuclear Engineering, Purdue University, 400 Central Drive, West Lafayette, IN 47907, USA
Ho Jun Yoon
Thermal-Hydraulics and Reactor Safety Laboratory, School of Nuclear Engineering, Purdue University, 400 Central Drive, West Lafayette, IN 47907, USA
Shripad Revankar
Purdue University

SINOPSIS

Several experiments have been performed in Purdue University Multi-Dimensional Integral Test Assembly (PUMA) facility to study the startup transient in a natural circulation BWR design. The strategy for the experimental study has been developed from pressure scaling based on single- and two-phase flow scaling laws. In the experiments, the differences of the stored energy of the solid structures and the core inlet subcooling between the facility and a natural circulation BWR design have been taken into account. A novel core inlet plate has been designed and installed to study the effect of the core inlet flow-loss coefficient on the startup instabilities, namely geysering and flashing-induced loop type oscillations. The experiments for the startup transient have been performed with and without considering the void-reactivity feedback. Based on a detailed analysis for the fuel heat conduction dynamics and neutron kinetics, the scaling criteria for the void-reactivity feedback simulation have been derived. By means of the local void fraction measurements with conductivity probes installed in the core section of the PUMA reactor pressure vessel, the void-reactivity feedback has been studied through the real-time solution of the point kinetic model equations. The presence of the void-reactivity coupling has been found to have a major destabilizing effect especially for the flashing-induced loop type oscillations.


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