Criticality and burn up evolutions of the Fixed Bed Nuclear Reactor with alternative fuels

Şahi̇n, Sümer; Şahi̇n, Hacı Mehmet; Acır, Adem

doi:10.1016/j.enconman.2009.12.044

Cited by 40 publications

(17 citation statements)

References 3 publications

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“…Several new MSR concepts have been proposed, such as the molten salt actinide recycler and transmuter (MOSART) system (Ignatiev et al, 2006) and the molten salt fast reactor (MSFR) (Merle-Lucotte et al, 2008). Because thorium could be a good alternative nuclear fuel (Sahin et al, 2010) and it has three times more abundant reserves than the natural uranium reserves, China has initiated a thorium-based molten salt reactor (TMSR) program, which was proposed by the Chinese Academy of Science in the strategic pilot science and technology special project "future advanced nuclear fission energy", aimed at opening up a road of innovation in line with China's national conditions for large-scale development of nuclear energy (SINAP, 2012).…”

Section: Introductionmentioning

confidence: 99%

Development of a kinetic model for safety studies of liquid-fuel reactors

Zhang

Rineiski

Zhang

et al. 2015

Progress in Nuclear Energy

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Section: Introductionmentioning

confidence: 99%

Development of a kinetic model for safety studies of liquid-fuel reactors

Zhang

Rineiski

Zhang

et al. 2015

Progress in Nuclear Energy

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“…And fast-spectrum MSRs fueled with plutonium and even minor actinides from LWR make possible nuclear waste burning. 7 Because thorium could be a good alternative nuclear fuel 8 and it has 3 times more abundant reserves than the natural uranium reserves, China has initiated a thoriumbased moltensalt reactor (TMSR) program, which was proposed by the Chinese Academy of Sciences in the strategic pilot science and technology special project "future advanced nuclear fission energy,", aimed at opening up a road of innovation in line with China's national conditions for large-scale development of nuclear energy. Online processing can minimize the fissile inventories and the radiation damage limit on the fuel burnup.…”

Section: Introductionmentioning

confidence: 99%

“…In addition, the FHR is expected to improve economics through air-Brayton combined cycle. 7 Because thorium could be a good alternative nuclear fuel 8 and it has 3 times more abundant reserves than the natural uranium reserves, China has initiated a thoriumbased moltensalt reactor (TMSR) program, which was proposed by the Chinese Academy of Sciences in the strategic pilot science and technology special project "future advanced nuclear fission energy,", aimed at opening up a road of innovation in line with China's national conditions for large-scale development of nuclear energy. 9 Earlier before this national TMSR project launching, XJTU was financially supported by the Natural Science Foundation of China to perform the fundamental research on the neutronics, thermal-hydraulic modeling, and safety analysis of MSRs.…”

Section: Introductionmentioning

confidence: 99%

Review of conceptual design and fundamental research of molten salt reactors in China

Zhang

Liu

et al. 2018

Int J Energy Res

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Summary Molten salt reactor (MSR) as 1 candidate of the generation IV advanced nuclear power systems attracted more attention in China due to its top ranked in fuel cycle and thorium utilization. Two types of MSR concepts were studied and developed in parallel, namely the MSR with liquid fuel and that with solid fuel. Abundant fundamental research including the neutronics modeling, thermal‐hydraulics modeling, safety analysis, material investigation, molten salts technologies etc. were carried out. Some analysis software such as COUPLE and FANCY were developed. Several experimental facilities like high‐temperature fluoride salt experiment loop have been constructed. Some passive residual heat removal systems were designed, and 1 test facility is under construction. The key MSR techniques including the extraction and separation of molten salt and construction of N‐base alloy have been mastered. Based on these fundamental research, Chinese Academy of Sciences has completed the design of thorium‐based MSRs with solid fuel and liquid fuel and is promoting their construction in the near future. In China, future efforts should be paid to the material, online fuel processing, Th‐U fuel cycle, component design, and construction and thermal‐hydraulic experiments for MSR, which are rather challenging nowadays.

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“…Recently, a number of studies have been conducted to search the possibility of further exploitation of these precious RG-Pu and MA in heavy water or graphite moderated nuclear reactors, having a better neutron economy than LWRs. Previous work has investigated intensively the utilization potential of RG-Pu and MA in the form of a mixed ThO 2 /PuO 2 fuel in CANDU reactors and fixed bed nuclear reactors [10][11][12][13][14][15][16][17][18]. These studies have been conducted under consideration of the transmutation and radioactive decay of all heavy metal isotopes with high precision in S 8 -P 3 energy groups using 238 neutron groups.…”

Section: Introductionmentioning

confidence: 99%

Utilization of nuclear waste plutonium and thorium mixed fuel in candu reactors

Şahi̇n

Şarer

Çelik

2016

Int. J. Energy Res.

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SUMMARYSpent nuclear fuel out of conventional light water reactors contains significant amount of even plutonium isotopes, so called reactor grade plutonium. Excellent neutron economy of Canada deuterium uranium (CANDU) reactors can further burn reactor grade plutonium, which has been used as a booster fissile fuel material in form of mixed ThO 2 /PuO 2 fuel in a CANDU fuel bundle in order to assure reactor criticality. The paper investigates incineration of nuclear waste and the prospects of exploitation of rich world thorium reserves in CANDU reactors.In the present work, the criticality calculations have been performed with 3-D geometrical modeling of a CANDU reactor, where the structure of all fuel rods and bundles is represented individually. In the course of time calculations, nuclear transformation and radioactive decay of all actinide elements as well as fission products are considered.Four different fuel compositions have been selected for investigations: ① 95% thoria (ThO 2 ) + 5% PuO 2 , ② 90% ThO 2 + 10% PuO 2 , ③ 85% ThO 2 + 15% PuO 2 and ④ 80% ThO 2 + 20% PuO 2 . The latter is used for the purpose of denaturing the new 233 U fuel with 238 U. The behavior of the criticality k ∞ and the burnup values of the reactor have been pursued by full power operation for~10 years.Among the investigated four modes, 90% ThO 2 + 10% PuO 2 seems a reasonable choice. This mixed fuel would continue make possible extensive exploitation of thorium resources with respect to reactor criticality. Reactor will run with the same fuel charge for~7 years and allow a fuel burnup~55 GWd/t.

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Criticality and burn up evolutions of the Fixed Bed Nuclear Reactor with alternative fuels

Cited by 40 publications

References 3 publications

Development of a kinetic model for safety studies of liquid-fuel reactors

Development of a kinetic model for safety studies of liquid-fuel reactors

Review of conceptual design and fundamental research of molten salt reactors in China

Utilization of nuclear waste plutonium and thorium mixed fuel in candu reactors

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