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Featured researches published by Ding She.


Nuclear Science and Engineering | 2012

Asymptotic Wielandt Method and Superhistory Method for Source Convergence in Monte Carlo Criticality Calculation

Ding She; Kan Wang; Ganglin Yu

Abstract In loosely coupled systems and large-scale systems, Monte Carlo criticality calculation suffers from slow fission source convergence because of the high dominance ratio (DR). In previous work, the Wielandt method and the superhistory method have been separately proposed to accelerate source convergence. However, although both methods decrease the DR, they are found not able to sufficiently accelerate fission source convergence. In this paper, the effective DR is defined and used to analyze the effectiveness of the Wielandt method and the superhistory method and to theoretically prove that they cannot reduce the computational time to converge the fission source. Accordingly, both methods are modified by adjusting the source population of inactive cycles, and their efficiency after adjustment is also compared. Moreover, the asymptotic Wielandt method (AWM) and the asymptotic superhistory method (ASM) are proposed, and the rules of deciding asymptotic parameters are also discussed. The new methods are implemented into the RMC code and validated by calculating loosely coupled problems and large-scale problems. Numerical calculation results show that AWM and ASM are practical and efficient for source convergence acceleration, which can save 75% to 90% of the computational time to reach a converged fission source.


Nuclear Science and Engineering | 2017

An Equivalent Homogenization Method for Treating the Stochastic Media

Ding She; Zhihong Liu; Lei Shi

Dispersion fuel is used in high-temperature reactors (HTRs) and some other advanced reactors. It contains a stochastic mixture of microsphere fuel grains or burnable poison grains embedded in a matrix material, which leads to the so-called double heterogeneity problem in the neutron transport calculation. This work investigates an equivalent homogenization method to deal with the stochastic media. In this method, the stochastic media are transformed to a homogenized material by introducing spatial self-shielding factors and preserving first-collision probabilities. A transmission model is proposed to calculate the first-collision probabilities and the self-shielding factors. In addition, the method is extended to treat the stochastic media with multitype grains. The applicability and correction techniques for the proposed method are discussed. The proposed method has been implemented in a lattice physics code named XPZ for HTRs. Numerical results are presented for typical HTR fuel pebbles and are validated against Monte Carlo solutions. It is concluded that the proposed equivalent homogenization method is promising for treating the double-heterogeneity problem and can be conveniently implemented in existing lattice physics codes.


18th International Conference on Nuclear Engineering: Volume 2 | 2010

RMC1.0: Development of Monte Carlo Code for Reactor Analysis

Ding She; Qi Xu; Kan Wang; Ganglin Yu

This paper describes a newly developed Monte Carlo code used for reactor analysis called RMC1.0, which is based on ACE format library. RMC1.0 is able to estimate criticality eigenvalue, and tally flux/spectrum with collision estimation method or tracking length method. Series of benchmarks and other examples are calculated for validation, which prove that RMC1.0 gives a good performance in both accuracy and efficiency compared with mcnp5. Despite its limitation in geometry processing, RMC1.0 has made a profitable attempt in self-development of Monte Carlo code for reactor analysis.Copyright


international conference on supercomputing | 2014

RMC - A Monte Carlo Code for Reactor Core Analysis

Kan Wang; Zeguang Li; Ding She; Jin’gang Liang; Qi Xu; Yishu Qiu; Jiankai Yu; Jialong Sun; Xiao Fan; Ganglin Yu


Annals of Nuclear Energy | 2015

RMC – A Monte Carlo code for reactor core analysis

Kan Wang; Zeguang Li; Ding She; Jin’gang Liang; Qi Xu; Yishu Qiu; Jiankai Yu; Jialong Sun; Xiao Fan; Ganglin Yu


Annals of Nuclear Energy | 2013

Development of burnup methods and capabilities in Monte Carlo code RMC

Ding She; Yuxuan Liu; Kan Wang; Ganglin Yu; Benoit Forget; Paul K. Romano; Kord Smith


Annals of Nuclear Energy | 2015

Development of random geometry capability in RMC code for stochastic media analysis

Shichang Liu; Ding She; Jingang Liang; Kan Wang


Annals of Nuclear Energy | 2014

2D full-core Monte Carlo pin-by-pin burnup calculations with the RMC code

Ding She; Jingang Liang; Kan Wang; Benoit Forget


Nuclear Engineering and Design | 2013

Development of the point-depletion code DEPTH

Ding She; Kan Wang; Ganglin Yu


Annals of Nuclear Energy | 2011

Optimization treatment of point-wise nuclear data in Monte Carlo criticality and burnup calculations

Yuxuan Liu; Ding She; Kan Wang; Ganglin Yu

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Qi Xu

Tsinghua University

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