Neutronics and material attractiveness for PWR thorium systems using monte carlo techniques

Trellue, Holly R.; Bathke, C.G.; Sadasivan, P.

doi:10.1016/j.pnucene.2011.04.007

Cited by 36 publications

(13 citation statements)

References 5 publications

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“…Thorium is said to be between three to four times more abundant than uranium (Trellue et al, 2011;WNA, 2011). Thorium-based fuels have greater potential to produce more fuel material (uranium) in reactors compared to uranium-based fuels producing fuel material plutonium (Kang-Mok & Myung-Hyung, 2005).…”

Section: Advantages Of Thorium-based Fuelmentioning

confidence: 99%

“…Thorium-based fuels have greater potential to produce more fuel material (uranium) in reactors compared to uranium-based fuels producing fuel material plutonium (Kang-Mok & Myung-Hyung, 2005). Uranium produced from thorium has better fuel properties to enhance reactor safety, and to efficiently generate electricity (Trellue et al, 2011). Thorium dioxide (ThO 2 ) is more stable and robust than Uranium dioxide (UO 2 ) in fuel fabrication fuel from a metallurgical (Caner & Dugan, 2000) and chemical point of view.…”

Section: Advantages Of Thorium-based Fuelmentioning

confidence: 99%

“…Thorium deployment in nuclear power reactors has been studied during the 1950s, but was not commonly employed due to the abundance and also lower cost of mining uranium (Trellue et al, 2011). There is a renewed interest in thorium for reasons elaborated in Section 1.1 and the International Atomic Energy Agency (IAEA) has released several reports on thorium utilization in nuclear reactors (IAEA, 2000;IAEA, 2002;IAEA, 2003;IAEA, 2005).…”

Section: Introductionmentioning

confidence: 99%

“…There is a renewed interest in thorium for reasons elaborated in Section 1.1 and the International Atomic Energy Agency (IAEA) has released several reports on thorium utilization in nuclear reactors (IAEA, 2000;IAEA, 2002;IAEA, 2003;IAEA, 2005). The feasibility of mixing thorium and plutonium fuel in existing PWRs has been the focus of some recent studies (Trellue et al, 2011;Fridman & Kliem, 2011;Bjork, 2012). This fuel mix is especially used to optimize the plutonium destruction rate (Schram & Klaassen, 2007).…”

Section: Introductionmentioning

confidence: 99%

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Proposal for improved nuclear fuel utilisation and economic performance by utilising thorium

Toit

Chirayath²

2017

J. energy South. Afr.

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A systematic and strategic nuclear power reactor deployment roadmap has been developed for South Africa within the national strategic plan, utilizing thorium-based fuel. The roadmap was developed through analysis of economical, strategic and historical aspects. The accumulated advantages of thorium-based fuels are summarized, which could form the initiative to implement thorium-based nuclear fuels in South Africa. A timeline (which forms the basis of the roadmap) was constructed and consists of three different phases. Phase 1 starts in 2015 and extends to 2030. Phase 2 starts in 2031 and ends in 2044 whilst Phase 3 is from 2045 to 2060. Each phase is discussed with regard to construction, implementation and research activities. This roadmap starts at current pressurized water reactors (PWRs) and advances to future reactor technologies, using an evolutionary approach. In addition to the results reported in this paper, the economic advantages to introducing thorium as a fertile component in PWR fuels as compared to once-through conventional uranium-only cycles is explored (Du Toit & Cilliers, 2014). The economic evaluation compares uranium fuel to thorium-uranium fuel in terms of the fuel cycle costs, reactor downtime costs due to refuelling and income derived from electricity sales.

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Section: Advantages Of Thorium-based Fuelmentioning

confidence: 99%

Section: Advantages Of Thorium-based Fuelmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

See 2 more Smart Citations

Proposal for improved nuclear fuel utilisation and economic performance by utilising thorium

Toit

Chirayath²

2017

J. energy South. Afr.

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“…Bjork et al studied the use of Th-Pu fuel for extending the operating cycle of a PWR . Trellue et al have used MCNP and MCNPX to compare the reactivity safety characteristics and Pu destruction capabilities of conventional MOX fuel to those of Th-MOX fuel (Trellue et al, 2011). Their work is complemented by that of Tsige-Tamirat, who also used Monte Carlo techniques to study the effect of Th-MOX fuel on a PWR's reactivity safety characteristics (Tsige-Tamirat, 2011).…”

Section: Introductionmentioning

confidence: 99%

Thorium-based mixed oxide fuel in a pressurized water reactor: A beginning of life feasibility analysis with MCNP

Tucker

Alajo

Usman

2015

Annals of Nuclear Energy

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Burn‐up calculation of the neutronic and safety parameters of thorium‐uranium mixed oxide fuel cycle in a Westinghouse small modular reactor

et al. 2020

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Summary Thorium fuel is presently a globally known future nuclear fuel alternative, having good neutronic, physical and chemical properties in addition to its spent nuclear fuel characteristic proliferation resistance. This research focused on the neutronic and safety parameters of thorium‐uranium mixed oxide fuel cycle, utilising three fissile enrichment zones, a departure from the conventional single enrichment. The aim was to determine the range of three fissile zones adequate for thorium‐uranium fuel cycle; investigating the performance efficiency of the fuel neutronic and inherent safety parameters in response to temperature differentials, which determines the viability of the fuel and core composition. Use was made of the MCNPX 2.7 code integrated with the CINDER90 fuel depletion code for steady‐state and burn‐up calculations. The keff, moderator temperature coefficient (MTC) and fuel temperature coefficient (FTC) of reactivity are affected by the range of fissile enrichment and fuel temperature which decreased with their respective increases. The MTC for all the moderator temperatures was within 0 to −40 pcm/K design value for UO2 fuel. Similarly, the FTC was within −3.5 to −1 pcm/K design value for all the fuel temperatures except after 2000 days, where a positive reactivity feedback was introduced. At ~86 MWd/kgHM single discharge burn‐up, the result shows that ~90% of the initial fissile load was utilised for energy production at the normal reactor operating temperature (600 K) with a slight reduction at higher fuel temperature. The total fissile inventory ratio (FIR), 233U/kg‐232Th and 239Pu/kg‐238U inventory ratios were significantly large and increased with burn‐up. It is remarkable that the FIR and the 233U/kg‐232Th inventory ratio did not reach conversion equilibrium until exit burn‐up. The large percentage fuel utilisation supports the advantage of fissile enrichment zoning in a thermal nuclear reactor core, making the chosen novel three fissile enrichment zones for thorium‐uranium fuel cycle reliable.

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Neutronics and material attractiveness for PWR thorium systems using monte carlo techniques

Cited by 36 publications

References 5 publications

Proposal for improved nuclear fuel utilisation and economic performance by utilising thorium

Proposal for improved nuclear fuel utilisation and economic performance by utilising thorium

Thorium-based mixed oxide fuel in a pressurized water reactor: A beginning of life feasibility analysis with MCNP

Burn‐up calculation of the neutronic and safety parameters of thorium‐uranium mixed oxide fuel cycle in a Westinghouse small modular reactor

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