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Multi-Level Methods for Monte Carlo Reactor Kinetics- [electronic resource]
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Multi-Level Methods for Monte Carlo Reactor Kinetics- [electronic resource]
자료유형  
 학위논문
Control Number  
0016933628
International Standard Book Number  
9798379564971
Dewey Decimal Classification Number  
539.76
Main Entry-Personal Name  
Gonzalez, Evan S.
Publication, Distribution, etc. (Imprint  
[S.l.] : University of Michigan., 2023
Publication, Distribution, etc. (Imprint  
Ann Arbor : ProQuest Dissertations & Theses, 2023
Physical Description  
1 online resource(184 p.)
General Note  
Source: Dissertations Abstracts International, Volume: 84-12, Section: B.
General Note  
Advisor: Kiedrowski, Brian C.
Dissertation Note  
Thesis (Ph.D.)--University of Michigan, 2023.
Restrictions on Access Note  
This item must not be sold to any third party vendors.
Restrictions on Access Note  
This item must not be added to any third party search indexes.
Summary, Etc.  
요약This dissertation develops methods to make time-dependent Monte Carlo transport calculations for reactor analysis more tractable. For the first time, the Transient Multi-Level (TML) method is applied to a Monte Carlo transport solver to offload some of the computational burden to lower-order Coarse Mesh Finite Difference (CMFD) and Exact Point Kinetics Equations (EPKE) solvers. The method is implemented in the production-level Monte Carlo code Shift and verified with select 2D transient events from the C5G7-TD reactor benchmark. It is shown that, as compared to other quasi-static methods, the TML reduces both the stochastic noise inherent to the Monte Carlo solver, and the number of Monte Carlo evaluations needed to simulate the transient. A step reactivity insertion for a 3D dual-purpose used nuclear fuel canister was also modeled with approximate fuel temperature Doppler broadening to stress the robustness of the method for large asymmetric configurations. Two techniques for acceleration of the Monte Carlo TML implementation are also explored: parallel- in-time integration and correlated sampling for fission source perturbations. A serial implementation of the parareal algorithm was investigated as a novel acceleration scheme between TML levels. The method converged very quickly for all cases in less than five parareal iterations with projected speedup factors (upon a parallel implementation) ranging from 1.5-8 for the evaluated problems. For correlated sampling, a fission source weighting technique for estimating multiple k-eigenvalue perturbation tallies for a single random walk was extended to general Monte Carlo tallies and shown to be a good approximation for spatially-uniform perturbations. These perturbation tallies can then be used as input for the CMFD and EPKE solvers and serve as a coarse prediction of the propagated Monte Carlo solution.
Subject Added Entry-Topical Term  
Nuclear engineering.
Subject Added Entry-Topical Term  
Thermodynamics.
Index Term-Uncontrolled  
Reactor kinetics
Index Term-Uncontrolled  
Monte Carlo solution
Index Term-Uncontrolled  
Quasi-static methods
Index Term-Uncontrolled  
Parareal algorithm
Added Entry-Corporate Name  
University of Michigan Nuclear Engineering & Radiological Sciences
Host Item Entry  
Dissertations Abstracts International. 84-12B.
Host Item Entry  
Dissertation Abstract International
Electronic Location and Access  
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Control Number  
joongbu:643495
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