Comparison of Neutronics-Depletion Coupling Schemes for Burnup Calculations

Isotalo, Aarno; Sahlberg, Ville

doi:10.13182/nse14-35

Cited by 25 publications

(19 citation statements)

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“…In the calculations of this study, the Bateman depletion equations were solved using the matrix exponential method based on the Chebyshev Rational Approximation Method (CRAM) [14,15,16], which is used by default in SERPENT. In the burn-up calculation, SERPENT code uses an internal routine for solving a set of Bateman equations, which are formulated as [14]:…”

Section: Methodsmentioning

confidence: 99%

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Neutronic Analysis of a Thorium-Fueled Reduced Moderation Boiling Water Reactor

Falaakh¹,

Agung²,

Harto³

2018

International Journal on Advanced Science, Engineering and Information Technology

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Abstract-A study about Resource Renewable Boiling Water Reactor (RBWR) core, a reduced moderation boiling water reactor that features the breeding ratio larger than 1 was conducted. This study focuses on the neutronic performances of the core and aims to investigate the core sustainability when using thorium as the main fertile fuel. A fuel-self-sustaining core with high burnup set as the design target. 233 U+Th were used as the initial fuel, and the impact of initial fissile ( 233 U) content in the core fissile zone on the core neutronic performances was evaluated. Parameters related to the neutronic performances such as the core burnup, fissile breeding, and fissile inventory ratio (FIR) are considered in this study. From these results, it was confirmed that it is feasible to create a selfsustaining fuel cycle system using thorium fueled RBWR. However, there was a trade-off between the core burnup and fissile breeding that can be a significant challenge in the development of this system. Evaluating the other design variables may be considered to address this challenge. The further study to analyze the safety performances of the core is required to arrive at a safe and reliable reactor system.

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Section: Methodsmentioning

confidence: 99%

“…In the burn-up calculation, SERPENT code uses an internal routine for solving a set of Bateman equations, which are formulated as [14]:…”

Section: Methodsmentioning

confidence: 99%

See 1 more Smart Citation

Neutronic Analysis of a Thorium-Fueled Reduced Moderation Boiling Water Reactor

Falaakh¹,

Agung²,

Harto³

2018

International Journal on Advanced Science, Engineering and Information Technology

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“…The middle-of-step nuclide concentrations, C n+1/2 , are only used to calculate a more accurate estimate of the time-averaged fluxes. The accuracy of this middlestep method has recently been investigated [26,27]. These studies show that the accuracy of this method can be adequate for many problems.…”

Section: Depletion Packagementioning

confidence: 99%

Implementation, capabilities, and benchmarking of Shift, a massively parallel Monte Carlo radiation transport code

Pandya

Johnson

Evans

et al. 2016

Journal of Computational Physics

116

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This work discusses the implementation, capabilities, and validation of Shift, a massively parallel Monte Carlo radiation transport package authored at Oak Ridge National Laboratory. Shift has been developed to scale well from laptops to small computing clusters to advanced supercomputers and includes features such as support for multiple geometry and physics engines, hybrid capabilities for variance reduction methods such as the Consistent Adjoint-Driven Importance Sampling methodology, advanced parallel decompositions, and tally methods optimized for scalability on supercomputing architectures. The scaling studies presented in this paper demonstrate good weak and strong scaling behavior for the implemented algorithms. Shift has also been validated and verified against various reactor physics benchmarks, including the Consortium for Advanced Simulation of Light Water Reactors'

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“…This paper explores three questions related to renormalization in constant power burnup calculations: how should it be performed, how much of a difference does it make, and does considering it affect the conclusions of Isotalo and Sahlberg (2015) and Isotalo (2015a) regarding the advantage of the higher order neutronics-depletion coupling schemes (Isotalo and Aarnio, 2011a,b) over older methods.…”

Section: Introductionmentioning

confidence: 99%

Flux renormalization in constant power burnup calculations

Isotalo

Davidson

Pandya

et al. 2016

Annals of Nuclear Energy

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To more accurately represent the desired power in a constant power burnup calculation, the depletion steps of the calculation can be divided into substeps and the neutron flux renormalized on each substep to match the desired power. This paper explores how such renormalization should be performed, how large a difference it makes, and whether using renormalization affects results regarding the relative performance of different neutronics-depletion coupling schemes. When used with older coupling schemes, renormalization can provide a considerable improvement in overall accuracy. With previously published higher order coupling schemes, which are more accurate to begin with, renormalization has a much smaller effect. While renormalization narrows the differences in the accuracies of different coupling schemes, their order of accuracy is not affected.

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Comparison of Neutronics-Depletion Coupling Schemes for Burnup Calculations

Cited by 25 publications

References 0 publications

Neutronic Analysis of a Thorium-Fueled Reduced Moderation Boiling Water Reactor

Neutronic Analysis of a Thorium-Fueled Reduced Moderation Boiling Water Reactor

Implementation, capabilities, and benchmarking of Shift, a massively parallel Monte Carlo radiation transport code

Flux renormalization in constant power burnup calculations

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