Homogenized cross-section generation for pebble-bed type high-temperature gas-cooled reactor using NECP-MCX

In the two-step analysis of Pebble-Bed type High-Temperature Gas-Cooled Reactor (PB-HTGR), the lattice physics calculation for the generation of homogenized cross-sections is based on the fuel pebble. However, the randomly-dispersed fuel particles in the fuel pebble introduce double heterogeneity an...

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Main Authors: Shuai Qin, Yunzhao Li, Qingming He, Liangzhi Cao, Yongping Wang, Yuxuan Wu, Hongchun Wu
Format: Article
Language:English
Published: Elsevier 2023-09-01
Series:Nuclear Engineering and Technology
Subjects:
Online Access:http://www.sciencedirect.com/science/article/pii/S1738573323002553
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author Shuai Qin
Yunzhao Li
Qingming He
Liangzhi Cao
Yongping Wang
Yuxuan Wu
Hongchun Wu
author_facet Shuai Qin
Yunzhao Li
Qingming He
Liangzhi Cao
Yongping Wang
Yuxuan Wu
Hongchun Wu
author_sort Shuai Qin
collection DOAJ
description In the two-step analysis of Pebble-Bed type High-Temperature Gas-Cooled Reactor (PB-HTGR), the lattice physics calculation for the generation of homogenized cross-sections is based on the fuel pebble. However, the randomly-dispersed fuel particles in the fuel pebble introduce double heterogeneity and randomness. Compared to the deterministic method, the Monte Carlo method which is flexible in geometry modeling provides a high-fidelity treatment. Therefore, the Monte Carlo code NECP-MCX is extended in this study to perform the lattice physics calculation of the PB-HTGR. Firstly, the capability for the simulation of randomly-dispersed media, using the explicit modeling approach, is developed in NECP-MCX. Secondly, the capability for the generation of the homogenized cross-section is also developed in NECP-MCX. Finally, simplified PB-HTGR problems are calculated by a two-step neutronics analysis tool based on Monte Carlo homogenization. For the pebble beds mixed by fuel pebble and graphite pebble, the bias is less than 100 pcm when compared to the high-fidelity model, and the bias is increased to 269 pcm for pebble bed mixed by depleted fuel pebble. Numerical results show that the Monte Carlo lattice physics calculation for the two-step analysis of PB-HTGR is feasible.
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spelling doaj.art-ee5fb68f97b84bd1b5894b9cf9095ffe2023-08-25T04:24:01ZengElsevierNuclear Engineering and Technology1738-57332023-09-0155934503463Homogenized cross-section generation for pebble-bed type high-temperature gas-cooled reactor using NECP-MCXShuai Qin0Yunzhao Li1Qingming He2Liangzhi Cao3Yongping Wang4Yuxuan Wu5Hongchun Wu6School of Nuclear Science and Technology, Xi'an Jiaotong University, 28 West Xianning Road, Xi'an, Shaanxi, 710049, ChinaSchool of Nuclear Science and Technology, Xi'an Jiaotong University, 28 West Xianning Road, Xi'an, Shaanxi, 710049, ChinaCorresponding author.; School of Nuclear Science and Technology, Xi'an Jiaotong University, 28 West Xianning Road, Xi'an, Shaanxi, 710049, ChinaSchool of Nuclear Science and Technology, Xi'an Jiaotong University, 28 West Xianning Road, Xi'an, Shaanxi, 710049, ChinaSchool of Nuclear Science and Technology, Xi'an Jiaotong University, 28 West Xianning Road, Xi'an, Shaanxi, 710049, ChinaSchool of Nuclear Science and Technology, Xi'an Jiaotong University, 28 West Xianning Road, Xi'an, Shaanxi, 710049, ChinaSchool of Nuclear Science and Technology, Xi'an Jiaotong University, 28 West Xianning Road, Xi'an, Shaanxi, 710049, ChinaIn the two-step analysis of Pebble-Bed type High-Temperature Gas-Cooled Reactor (PB-HTGR), the lattice physics calculation for the generation of homogenized cross-sections is based on the fuel pebble. However, the randomly-dispersed fuel particles in the fuel pebble introduce double heterogeneity and randomness. Compared to the deterministic method, the Monte Carlo method which is flexible in geometry modeling provides a high-fidelity treatment. Therefore, the Monte Carlo code NECP-MCX is extended in this study to perform the lattice physics calculation of the PB-HTGR. Firstly, the capability for the simulation of randomly-dispersed media, using the explicit modeling approach, is developed in NECP-MCX. Secondly, the capability for the generation of the homogenized cross-section is also developed in NECP-MCX. Finally, simplified PB-HTGR problems are calculated by a two-step neutronics analysis tool based on Monte Carlo homogenization. For the pebble beds mixed by fuel pebble and graphite pebble, the bias is less than 100 pcm when compared to the high-fidelity model, and the bias is increased to 269 pcm for pebble bed mixed by depleted fuel pebble. Numerical results show that the Monte Carlo lattice physics calculation for the two-step analysis of PB-HTGR is feasible.http://www.sciencedirect.com/science/article/pii/S1738573323002553Pebble-bedMonte CarloNECP-MCXHomogenization
spellingShingle Shuai Qin
Yunzhao Li
Qingming He
Liangzhi Cao
Yongping Wang
Yuxuan Wu
Hongchun Wu
Homogenized cross-section generation for pebble-bed type high-temperature gas-cooled reactor using NECP-MCX
Nuclear Engineering and Technology
Pebble-bed
Monte Carlo
NECP-MCX
Homogenization
title Homogenized cross-section generation for pebble-bed type high-temperature gas-cooled reactor using NECP-MCX
title_full Homogenized cross-section generation for pebble-bed type high-temperature gas-cooled reactor using NECP-MCX
title_fullStr Homogenized cross-section generation for pebble-bed type high-temperature gas-cooled reactor using NECP-MCX
title_full_unstemmed Homogenized cross-section generation for pebble-bed type high-temperature gas-cooled reactor using NECP-MCX
title_short Homogenized cross-section generation for pebble-bed type high-temperature gas-cooled reactor using NECP-MCX
title_sort homogenized cross section generation for pebble bed type high temperature gas cooled reactor using necp mcx
topic Pebble-bed
Monte Carlo
NECP-MCX
Homogenization
url http://www.sciencedirect.com/science/article/pii/S1738573323002553
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