Linear modal analysis of out-of-phase instability in boiling water reactor cores

Hashimoto, Kazuo

doi:10.1016/0306-4549(93)90072-w

Cited by 57 publications

(13 citation statements)

References 16 publications

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“…In this study, two simulated fuel channels are used, representing two half-cylindrical cores, to demonstrate the fundamental mode, i.e., core-wide stability and the first-azimuthal mode, i.e., regional stability. Interactions between two simulated fuel channels are solved numerically to account for reactivity exchange between them (6) . A detailed formulation of the reactor neutronics is described in Ref.…”

Section: Design Conceptmentioning

confidence: 99%

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Stability Estimation of ABWR on the Basis of Noise Analysis

Furuya

Fukahori²,

Mizokami

et al. 2008

JPES

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In order to investigate the stability of a nuclear reactor core with an oxide mixture of uranium and plutonium (MOX) fuel installed, channel stability and regional stability tests were conducted with the SIRIUS-F facility. The SIRIUS-F facility was designed and constructed to provide a highly accurate simulation of thermal-hydraulic (channel) instabilities and coupled thermalhydraulics-neutronics instabilities of the Advanced Boiling Water Reactors (ABWRs). A real-time simulation was performed by 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 time series analysis was performed to calculate decay ratio and resonance frequency from a dominant pole of a transfer function by applying auto regressive (AR) methods to the time-series of the core inlet flow rate. Experiments were conducted with the SIRIUS-F facility, which simulates ABWR with MOX fuel installed. The variations in the decay ratio and resonance frequency among the five common AR methods are within 0.03 and 0.01 Hz, respectively. In this system, the appropriate decay ratio and resonance frequency can be estimated on the basis of the Yule-Walker method with the model order of 30.

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Section: Design Conceptmentioning

confidence: 99%

“…Hashimoto (6) derived the linearized formulation of reactor neutronics including the eigenvalue separation of the higher-harmonic neutronic mode, as follows:…”

Section: Neutronicsmentioning

confidence: 99%

Stability Estimation of ABWR on the Basis of Noise Analysis

Furuya

Fukahori²,

Mizokami

et al. 2008

JPES

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“…The neutron coupling property between core regions is quantitatively estimated by an eigenvalue separation that is defined by the difference between the inverses of the fundamental and the first order eigenvalues. 1,2) Therefore, for the analysis of the instability of a core, it is important to evaluate the first order eigenvalue.…”

Section: Introductionmentioning

confidence: 99%

Evaluation of Eigenvalue Separation by the Monte Carlo Method

Kitada

Takeda

2002

Journal of Nuclear Science and Technology

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A new technique for evaluating an eigenvalue separation by the Monte Carlo method is proposed. This technique uses a fission matrix evaluated by an ordinary Monte Carlo calculation and enables us to evaluate higher order eigenvalues and eigenvectors that have not been able to be determined by Monte Carlo calculation. To validate it, the proposed technique was applied to the analysis of the modeled BWR core and the coupled-core reactor assembled at the C-core tank of KUCA (Kyoto University Critical Assembly). Consequently, it was found that this new technique gave good results regarding eigenvalue separation, although regional division needs to be noted in a system for evaluating a fission matrix.

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“…6) Several frequency-domain stability analysis codes employing the modal neutron point kinetics model have been developed, which are capable of predicting the stability of regional oscillations within reasonable precision. 19,20) Hereafter, using the modal model proposed by Hashimoto,21) the potential nonlinear behavior in the simulated regional oscillation will be studied.…”

Section: Investigation By Modal Point Kinetics Theorymentioning

confidence: 99%

Nonlinear Behavior under Regional Neutron Flux Oscillations in BWR Cores

Ikeda

Ama

Hashimoto

et al. 2001

Journal of Nuclear Science and Technology

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A three-dimensional time-domain core analysis code was applied to numerical simulations for an actual regional neutron flux oscillation observed in a commercial BWR core, in order to investigate potential nonlinear behavior in its coupled neutronic and thermohydraulic system. The present study shows existence of the nonlinear reactivity interaction between the fundamental and first azimuthal spatial harmonics modes of neutron flux distribution under the regional event. The spectrum analysis of the simulated data provides a unique result, that is, temporal harmonics peaks are excited at the even-and odd-order multiples of the characteristic resonance frequency in the fundamental and first spatial harmonics responses, respectively. The numerical simulation also shows that the strong nonlinearity of the coupled neutronic and thermohydraulic dynamics locally appears where the power unstably oscillates with large amplitudes, inducing the power shift and reactivity bias which are shown in the core-wide situation under the global oscillations. This contributes to suppression of the divergence of the local power oscillation, and also to development of the saturated self-limited cycles under the regional oscillations.

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Linear modal analysis of out-of-phase instability in boiling water reactor cores

Cited by 57 publications

References 16 publications

Stability Estimation of ABWR on the Basis of Noise Analysis

Stability Estimation of ABWR on the Basis of Noise Analysis

Evaluation of Eigenvalue Separation by the Monte Carlo Method

Nonlinear Behavior under Regional Neutron Flux Oscillations in BWR Cores

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