Neutronic study of utilization of discrete thorium-uranium fuel pins in CANDU-6 reactor

Targeting at simulating the application of thorium-uranium (TU) fuel in the CANDU-6 reactor, this paper analyzes the process using the code DRAGON/DONJON where the discrete TU fuel pins are applied in the CANDU-6 reactor under the time-average equilibrium refueling. The results show that the coolant...

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Main Authors:	Nianbiao Deng, Tao Yu, Jinsen Xie, Zhenping Chen, Qin Xie, Pengcheng Zhao, Zijing Liu, Wenjie Zeng
Format:	Article
Language:	English
Published:	Elsevier 2019-04-01
Series:	Nuclear Engineering and Technology
Online Access:	http://www.sciencedirect.com/science/article/pii/S1738573318305321

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spelling	doaj-4386e77e64b94967bfb4f8a0ce12ed902020-11-24T21:09:37ZengElsevierNuclear Engineering and Technology1738-57332019-04-01512377383Neutronic study of utilization of discrete thorium-uranium fuel pins in CANDU-6 reactorNianbiao Deng0Tao Yu1Jinsen Xie2Zhenping Chen3Qin Xie4Pengcheng Zhao5Zijing Liu6Wenjie Zeng7School of Nuclear Science and Technology, University of South China, Hengyang, Hunan, 421001, PR China; Research Center for Digital Nuclear Reactor Engineering and Technology of Hunan Province, University of South China, Hengyang, Hunan, 421001, PR ChinaSchool of Nuclear Science and Technology, University of South China, Hengyang, Hunan, 421001, PR China; Research Center for Digital Nuclear Reactor Engineering and Technology of Hunan Province, University of South China, Hengyang, Hunan, 421001, PR China; Corresponding author. School of Nuclear Science and Technology, University of South China, Hengyang, Hunan, 421001, PR China.School of Nuclear Science and Technology, University of South China, Hengyang, Hunan, 421001, PR China; Research Center for Digital Nuclear Reactor Engineering and Technology of Hunan Province, University of South China, Hengyang, Hunan, 421001, PR ChinaSchool of Nuclear Science and Technology, University of South China, Hengyang, Hunan, 421001, PR China; Research Center for Digital Nuclear Reactor Engineering and Technology of Hunan Province, University of South China, Hengyang, Hunan, 421001, PR ChinaSchool of Nuclear Science and Technology, University of South China, Hengyang, Hunan, 421001, PR China; Research Center for Digital Nuclear Reactor Engineering and Technology of Hunan Province, University of South China, Hengyang, Hunan, 421001, PR ChinaSchool of Nuclear Science and Technology, University of South China, Hengyang, Hunan, 421001, PR China; Research Center for Digital Nuclear Reactor Engineering and Technology of Hunan Province, University of South China, Hengyang, Hunan, 421001, PR ChinaSchool of Nuclear Science and Technology, University of South China, Hengyang, Hunan, 421001, PR China; Research Center for Digital Nuclear Reactor Engineering and Technology of Hunan Province, University of South China, Hengyang, Hunan, 421001, PR ChinaSchool of Nuclear Science and Technology, University of South China, Hengyang, Hunan, 421001, PR China; Research Center for Digital Nuclear Reactor Engineering and Technology of Hunan Province, University of South China, Hengyang, Hunan, 421001, PR ChinaTargeting at simulating the application of thorium-uranium (TU) fuel in the CANDU-6 reactor, this paper analyzes the process using the code DRAGON/DONJON where the discrete TU fuel pins are applied in the CANDU-6 reactor under the time-average equilibrium refueling. The results show that the coolant void reactivity of the assembly analyzed in this paper is lower than that of 37-element bundle cell with natural uranium and 37-element bundle cell with mixed TU fuel pins; that the max time-average channel/bundle power of the core meets the limits - less than 6700kW/860 kW; that the fuel conversion ratio is higher than that of the CANDU-6 reactor with natural uranium; and that the exit burnup increases to 13400 MWd/tU. Thus, the simulation in this paper with the fuel in the 37-element bundle cell using discrete TU fuel pins can be considered to be applied in CANDU-6 reactor with adequate modifications of the core structure and operating modes. Keywords: Th-U fuel, CANDU, Assembly schemes, Core schemes, Time-average modelhttp://www.sciencedirect.com/science/article/pii/S1738573318305321
collection	DOAJ
language	English
format	Article
sources	DOAJ
author	Nianbiao Deng Tao Yu Jinsen Xie Zhenping Chen Qin Xie Pengcheng Zhao Zijing Liu Wenjie Zeng
spellingShingle	Nianbiao Deng Tao Yu Jinsen Xie Zhenping Chen Qin Xie Pengcheng Zhao Zijing Liu Wenjie Zeng Neutronic study of utilization of discrete thorium-uranium fuel pins in CANDU-6 reactor Nuclear Engineering and Technology
author_facet	Nianbiao Deng Tao Yu Jinsen Xie Zhenping Chen Qin Xie Pengcheng Zhao Zijing Liu Wenjie Zeng
author_sort	Nianbiao Deng
title	Neutronic study of utilization of discrete thorium-uranium fuel pins in CANDU-6 reactor
title_short	Neutronic study of utilization of discrete thorium-uranium fuel pins in CANDU-6 reactor
title_full	Neutronic study of utilization of discrete thorium-uranium fuel pins in CANDU-6 reactor
title_fullStr	Neutronic study of utilization of discrete thorium-uranium fuel pins in CANDU-6 reactor
title_full_unstemmed	Neutronic study of utilization of discrete thorium-uranium fuel pins in CANDU-6 reactor
title_sort	neutronic study of utilization of discrete thorium-uranium fuel pins in candu-6 reactor
publisher	Elsevier
series	Nuclear Engineering and Technology
issn	1738-5733
publishDate	2019-04-01
description	Targeting at simulating the application of thorium-uranium (TU) fuel in the CANDU-6 reactor, this paper analyzes the process using the code DRAGON/DONJON where the discrete TU fuel pins are applied in the CANDU-6 reactor under the time-average equilibrium refueling. The results show that the coolant void reactivity of the assembly analyzed in this paper is lower than that of 37-element bundle cell with natural uranium and 37-element bundle cell with mixed TU fuel pins; that the max time-average channel/bundle power of the core meets the limits - less than 6700kW/860 kW; that the fuel conversion ratio is higher than that of the CANDU-6 reactor with natural uranium; and that the exit burnup increases to 13400 MWd/tU. Thus, the simulation in this paper with the fuel in the 37-element bundle cell using discrete TU fuel pins can be considered to be applied in CANDU-6 reactor with adequate modifications of the core structure and operating modes. Keywords: Th-U fuel, CANDU, Assembly schemes, Core schemes, Time-average model
url	http://www.sciencedirect.com/science/article/pii/S1738573318305321
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Neutronic study of utilization of discrete thorium-uranium fuel pins in CANDU-6 reactor

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