Abstract
The ex-core detector-response calculation is a typical deep-penetration problem, which is challenging for the Monte Carlo method. The response of the ex-core detector is an important parameter for the safe operation of the nuclear power plants. Meanwhile, evaluation of the ex-core detector response during each step of fuel-loading is used to guide the fuel-loading sequence. The response can also be used to reconstruct core-power distribution for online monitoring of long-term power. The detector used for the ex-core response is the source-range detector which is sensitive to thermal neutrons. For a Monte Carlo shielding calculation of the above detector response, the thermal flux under 0.625eV is needed, which is too small to be tallied by traditional Monte Carlo simulations. In practice, the tally results are close to zero in the detector region under direct Monte Carlo calculation. Even if the number of particles is increased to a significant amount, the statistical variance is still very large. The high variance along with a significant calculation time leads to a small Figure Of Merit (FOM). In order to solve this problem and to improve the tally efficiency of the ex-core detector response, a hybrid Monte-Carlo-deterministic method is employed in this study, and an in-house hybrid Monte-Carlo-deterministic particle transport code, NECP-MCX, is developed in this paper. The method takes the space-energy-dependent adjoint fluxes to generate importance parameters for the mesh-based weight window in the Monte Carlo calculation. Simultaneously, the mesh-based source biasing is performed with the consistent importance parameters to make the starting weight of neutrons matching with the survival weight of the weight windows. As the mesh used in the hybrid Monte-Carlo-deterministic method is superimposed, the mesh of the weight window will not be affected by the complex geometry model. The adjoint flux is obtained by the efficient SN method with the multi-group cross-section data. The whole toolset is convenient to use with single set of the modelling data for both Monte Carlo and deterministic simulations. Compared with the direct Monte Carlo simulation, the hybrid Monte-Carlo-deterministic method has a higher efficiency for a typical deep-penetration problem such as the AP1000 ex-core detector-response simulation.
Highlights
AP1000 is a 1000MWe pressurized water reactor (PWR) with passive safety features
From the results shown above, the hybrid method in NECP-MCX performs very well in getting tally results with low statistical relative errors
The response results of AP1000 ex-core detectors simulated by NECP-MCX performs very well with small statistic relative errors
Summary
AP1000 is a 1000MWe pressurized water reactor (PWR) with passive safety features. During its commissioning/operation time, the response of ex-core detector is important for getting the information of commissioning/operation state. An accurate calculation of the detector response is essential for the core design and the state prediction before the commissioning/operation of the reactor [3]. Have been developed to handle this kind of problem The usage of these methods is empirical which needs extensive experiences and numerical iterations in order to get acceptable results. They are not convenient to use in lack of experience (e.g. the simulation of AP-1000 ex-core detector response during the commissioning phase). NECP-MCX can set the weight window and the source biasing automatically and it performs well with very high Figure Of Merit (FOM) when compared with the direct Monte Carlo simulation or the Monte Carlo calculation with the region-importance option. With NECP-MCX, the AP1000 ex-core detector response can be simulated accurately and efficiently without users’ experiences
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