Evaluating the Diffusion Approximation Capability on the Integral Pressurized Water Reactor (IPWR) Core Calculation

Diffusion approximation is an important approximation used to model a nuclear reactor core with a quite good accuracy and less computational cost. This approximation has been used widely around the globe for various kinds of nuclear reactors. This diffusion approximation is applied in a two-step met...

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Main Authors: H. Ardiansyah, M. R. Oktavian
Format: Article
Language:English
Published: Center for Development of Nuclear Informatics, National Nuclear Energy Agency (BATAN) 2021-07-01
Series:Atom Indonesia
Subjects:
Online Access:https://aij.batan.go.id/index.php/aij/article/view/1013
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spelling doaj-cb90e5ff4d8e47a49d6c63e9992939ac2021-08-12T06:00:39ZengCenter for Development of Nuclear Informatics, National Nuclear Energy Agency (BATAN)Atom Indonesia0126-15682021-07-01472859210.17146/aij.2021.1013441Evaluating the Diffusion Approximation Capability on the Integral Pressurized Water Reactor (IPWR) Core CalculationH. Ardiansyah0M. R. Oktavian1Department of Nuclear Engineering and Radiological Sciences, University of Michigan, 2355 Bonisteel Blvd, Ann Arbor, MI 48109, United States of America1. School of Nuclear Engineering, Purdue University, 516 Northwestern Ave., West Lafayette, IN 47906, United States of America 2. Department of Nuclear Engineering and Engineering Physics, Faculty of Engineering, Universitas Gadjah Mada, Jl. Grafika No. 2, Yogyakarta 55281, IndonesiaDiffusion approximation is an important approximation used to model a nuclear reactor core with a quite good accuracy and less computational cost. This approximation has been used widely around the globe for various kinds of nuclear reactors. This diffusion approximation is applied in a two-step method, a method combining a high fidelity transport code and low fidelity diffusion code. Meanwhile, innovations in the nuclear core model continue to make the nuclear reactor core safer, more robust, and smaller. The trend of creating smaller and more modular reactor core is emerging in the last ten years. These innovations will affect the core modeling system. Consequently, for smaller reactors, it is important to evaluate the capability of diffusion approximation if one wants to use a computationally cheaper method to model the reactor core. In this paper, neutron diffusion calculation for 160 MWth integral pressurized water reactor (IPWR) core was conducted using the PARCS nodal diffusion code employing the few-group spatially homogenized cross-sections generated by the Serpent Monte Carlo code. Due to its capability to model any reactor geometry in the high-resolution calculation, the results from Serpent were also used as a reference. Two important parameters are compared between PARCS and Serpent: effective neutron multiplication factor and core power distribution. For the full IPWR core model, a discrepancy of 564 pcm between PARCS and Serpent keff was observed, while the radial power distribution had a maximum error of 4.71 %. It can be said, to some extent, that the diffusion approximation can be applied to IPWR core analysis. However, further improvement is indeed required if one wants more accurate results with low computational costs.https://aij.batan.go.id/index.php/aij/article/view/1013diffusiontwo-step methodipwrparcsserpent
collection DOAJ
language English
format Article
sources DOAJ
author H. Ardiansyah
M. R. Oktavian
spellingShingle H. Ardiansyah
M. R. Oktavian
Evaluating the Diffusion Approximation Capability on the Integral Pressurized Water Reactor (IPWR) Core Calculation
Atom Indonesia
diffusion
two-step method
ipwr
parcs
serpent
author_facet H. Ardiansyah
M. R. Oktavian
author_sort H. Ardiansyah
title Evaluating the Diffusion Approximation Capability on the Integral Pressurized Water Reactor (IPWR) Core Calculation
title_short Evaluating the Diffusion Approximation Capability on the Integral Pressurized Water Reactor (IPWR) Core Calculation
title_full Evaluating the Diffusion Approximation Capability on the Integral Pressurized Water Reactor (IPWR) Core Calculation
title_fullStr Evaluating the Diffusion Approximation Capability on the Integral Pressurized Water Reactor (IPWR) Core Calculation
title_full_unstemmed Evaluating the Diffusion Approximation Capability on the Integral Pressurized Water Reactor (IPWR) Core Calculation
title_sort evaluating the diffusion approximation capability on the integral pressurized water reactor (ipwr) core calculation
publisher Center for Development of Nuclear Informatics, National Nuclear Energy Agency (BATAN)
series Atom Indonesia
issn 0126-1568
publishDate 2021-07-01
description Diffusion approximation is an important approximation used to model a nuclear reactor core with a quite good accuracy and less computational cost. This approximation has been used widely around the globe for various kinds of nuclear reactors. This diffusion approximation is applied in a two-step method, a method combining a high fidelity transport code and low fidelity diffusion code. Meanwhile, innovations in the nuclear core model continue to make the nuclear reactor core safer, more robust, and smaller. The trend of creating smaller and more modular reactor core is emerging in the last ten years. These innovations will affect the core modeling system. Consequently, for smaller reactors, it is important to evaluate the capability of diffusion approximation if one wants to use a computationally cheaper method to model the reactor core. In this paper, neutron diffusion calculation for 160 MWth integral pressurized water reactor (IPWR) core was conducted using the PARCS nodal diffusion code employing the few-group spatially homogenized cross-sections generated by the Serpent Monte Carlo code. Due to its capability to model any reactor geometry in the high-resolution calculation, the results from Serpent were also used as a reference. Two important parameters are compared between PARCS and Serpent: effective neutron multiplication factor and core power distribution. For the full IPWR core model, a discrepancy of 564 pcm between PARCS and Serpent keff was observed, while the radial power distribution had a maximum error of 4.71 %. It can be said, to some extent, that the diffusion approximation can be applied to IPWR core analysis. However, further improvement is indeed required if one wants more accurate results with low computational costs.
topic diffusion
two-step method
ipwr
parcs
serpent
url https://aij.batan.go.id/index.php/aij/article/view/1013
work_keys_str_mv AT hardiansyah evaluatingthediffusionapproximationcapabilityontheintegralpressurizedwaterreactoripwrcorecalculation
AT mroktavian evaluatingthediffusionapproximationcapabilityontheintegralpressurizedwaterreactoripwrcorecalculation
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