Viability of thorium-based nuclear fuel cycle for the next generation nuclear reactor: Issues and prospects

Humphrey, Uguru Edwin; Khandaker, Mayeen Uddin

doi:10.1016/j.rser.2018.08.019

Cited by 134 publications

(71 citation statements)

References 49 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…As with PWRs, it has been shown that Th-Pu MOX fuelled BWRs are viable options for existing as well as advanced designs (Humphrey & Khandaker, 2018) (Seifried, et al, 2015) (Ganda, et al, 2012). The harder spectrum of the BWR lends itself well to use with Th-fuels, because the higher conversion ratio of Th232 compared to U238 leads to lower fissile loading requirements to achieve a given discharge burnup when compared to U-MOX options.…”

Section: Transuranic (Tru) Waste Recycle In Bwrsmentioning

confidence: 99%

The effect of Am241 on UK plutonium recycle options in thorium-plutonium fuelled LWRs – Part II: BWRs

Morrison

Parks

2020

Annals of Nuclear Energy

View full text Add to dashboard Cite

UK plutonium is expected to be managed using uranium-plutonium (U-Pu) mixed oxide (MOX) fuels in Light Water Reactors (LWRs). However, studies have shown that thorium-plutonium (Th-Pu) may be preferential. Part I of this study considered the effect of americium (Am) in UK Pu in Pressurized Water Reactors (PWRs) and found that, while the reactivity response was sensitive to isotopic and spectral variations, trends were predictable. Part II focusses on separation of Am in Boiling Water Reactors (BWRs) and compares fuel performance to the uniformly distributed and spatially separated cases outlined in Part I. Comparable incineration rates are achievable but, while a single PWR assembly bears a greater mass of Am/Pu than a single BWR assembly, the full BWR core may be capable of operating with significantly greater fissile masses. Transmutation of Am241 to Am242 appears preferable to fast fission of Am241 as increased incineration occurs in lower void, bottom-of-assembly locations.

show abstract

Section: Transuranic (Tru) Waste Recycle In Bwrsmentioning

confidence: 99%

The effect of Am241 on UK plutonium recycle options in thorium-plutonium fuelled LWRs – Part II: BWRs

Morrison

Parks

2020

Annals of Nuclear Energy

View full text Add to dashboard Cite

show abstract

“…Although its initial weapon intention was not actualised which slowed down thorium research, the United States, India, China etc. remained committed in thorium research, leading to its utilisation in the Shippingport pressurised water reactor, Indian Point Reactor, Advanced Heavy Water Reactor and many other reactor designs as reported by Van Gosen, Tulsidas 4 and Humphrey, Khandaker 5 …”

Section: Introductionmentioning

confidence: 99%

“…This design has been used in the Russian Vodo‐Vodyanoi Energetichesky Reaktor (Water‐Water Energetic Reactor) Thorium (VVERT) reactor design, which posed a problem of using two different fuel management schemes for the core. Today, several other scientific studies and reports have revealed the potential of thorium dioxide as an alternative fuel resource, 5,8‐10 making interest in thorium‐based fuel cycle to remain strong due to its reported reduction in plutonium production, large abundance, proliferation resistant spent nuclear fuel, longer discharge burn‐up, high fuel melting temperature and conductivity, lower expansion coefficient and high thermal stability 11,12 . The conclusion was that the use of ThO 2 fuel similar to UO 2 fuel cycle in a homogeneous or heterogeneous thermal reactor core is not realistic and economically viable, making its use in a mixed oxide form most probable 13,14 …”

Section: Introductionmentioning

confidence: 99%

“…The conventional mixed oxide fuel (MOX) comprising of UO 2 blended with PuO 2 forming uranium‐plutonium mixed oxide fuel was considered for use of in the existing light water reactor designs 5,15 . The essence of MOX approach was to burn the stockpiled plutonium waste besides increasing fuel resource and decreasing the proliferation potential of nuclear waste and the risk of nuclear terrorism 15,16 .…”

Section: Introductionmentioning

confidence: 99%

See 1 more Smart Citation

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

View full text Add to dashboard Cite

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.

show abstract

“…The other strategy is to firstly separate the intermediate 233 Pa and store it to cool and naturally decay to 233 U. The latter method is a better choice because of the higher purity of the separated 233 U and less long-lived nuclides in use [6,8,9,10]. So far, this method is restricted by the necessity for fast-processing 233 Pa to reduce the irradiative danger and the possible interference of hazardous 231 Pa formed in thorium-uranium fuel cycle.…”

Section: Introductionmentioning

confidence: 99%

Density Functional Theory Investigations on the Mechanism of Formation of Pa(V) Ion in Hydrous Solutions

Yang

Han

et al. 2019

Molecules

View full text Add to dashboard Cite

Due to the enormous threat of protactinium to the environment and human health, its disposal and chemistry have long been important topics in nuclear science. [PaO(H2O)6]3+ is proposed as the predominant species in hydrous and acidic solutions, but little is known about its formation mechanism. In this study, density functional theory (DFT) calculations demonstrate a water coordination-proton transfer-water dissociation mechanism for the formation of PaO3+ in hydrous solutions. First, Pa(V) ion preferentially forms hydrated complexes with a coordination number of 10. Through hydrogen bonding, water molecules in the second coordination sphere easily capture two protons on the same coordinated H2O ligand to form [PaO(H2O)9]3+. Water dissociation then occurs to generate the final [PaO(H2O)6]3+, which is the thermodynamic product of Pa(V) in hydrous solutions.

show abstract

Viability of thorium-based nuclear fuel cycle for the next generation nuclear reactor: Issues and prospects

Cited by 134 publications

References 49 publications

The effect of Am241 on UK plutonium recycle options in thorium-plutonium fuelled LWRs – Part II: BWRs

The effect of Am241 on UK plutonium recycle options in thorium-plutonium fuelled LWRs – Part II: BWRs

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

Density Functional Theory Investigations on the Mechanism of Formation of Pa(V) Ion in Hydrous Solutions

Contact Info

Product

Resources

About