Spectrum shifting as a mechanism to improve performance of VHTRs with advanced actinide fuels

Tsvetkov, Pavel V.; Ames, David E.; Alajo, Ayodeji Babatunde; Lewis, Tom G.

doi:10.1016/j.nucengdes.2007.11.013

Cited by 8 publications

(6 citation statements)

References 6 publications

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“…The prismatic block assembly allows the flexibility of component configuration and fuel management, thus enabling configuration adjustments to achieve neutron spectrum shifting. This would lead to increased fuel utilization and extended operation in a single‐batch operation mode 57 . As shown in Figure 9, the average fuel block spectrum of different fuel block configurations transitions with increased burnup at BOC, middle of the cycle (MOC), and end of the cycle (EOC).…”

Section: Resultsmentioning

confidence: 99%

A neutronic investigation of tristructural isotropic‐duplex fuel in a high‐temperature reactor prismatic seed‐and‐blanket fuel block configuration with reduced power peaking

2021

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Summary This paper presents the neutronic analysis of a tristructural isotropic (TRISO)‐duplex fuel loaded into the high‐temperature reactor (HTR) prismatic fuel block designs for a seed‐and‐blanket (S&B) reactor model. The selected fuel block design is the simplified model of a representative fuel configuration for the gas turbine–module helium reactor (GT‐MHR) and high‐temperature engineering test reactor (HTTR). The duplex fuel pellet comprises of UO2 as the seed and ThO2 as the blanket and uses the TRISO fuels. Monte Carlo N‐particle extended (MCNPX) simulations were conducted to analyze the power and neutron flux distributions of the reference fuel block and that of the TRIOS‐loaded duplex fuel designs. Standard neutronic parameters were computed, such as burnup‐dependent infinite multiplication factors (kinf), average block spectrum, and fissile inventory. It was discovered that while the S&B model could attain the highest burnup and the longest cycle duration, its power peaking was more than threefolds than that of the reference model at the beginning of the cycle (BOC). The results also show that the “Duplex‐2” model could reduce its power peaking by 24% through the integration of S&B arrangement with the duplex rods. It is noted that spatial distribution of the UO2 seed and 235U enrichment are the chief determining factors in the power optimization of the heterogeneous HTR prismatic fuel blocks loaded with thorium.

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Section: Resultsmentioning

confidence: 99%

A neutronic investigation of tristructural isotropic‐duplex fuel in a high‐temperature reactor prismatic seed‐and‐blanket fuel block configuration with reduced power peaking

2021

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“…Table 1 summarizes parameters of the reference VHTR design. To assure comprehensive and realistic assessment, extensive benchmark evaluations were performed based on the HTTR experimental program results [4,10]. Obtained benchmark results are in agreement with the available HTTR data and confirm applicability of the chosen modeling approach as it described in what follows [4].…”

Section: Reference Vhtr Configurationmentioning

confidence: 56%

“…The fundamental building blocks of the reactor (e.g., fuel blocks and its constituents) and the ratio of these blocks (control rod guide blocks to fuel block ratio) to one another are based on HTTR design parameters, while the overall configuration of the reactor has been developed following the DOE VHTR design requirements. The modeling adequacy is confirmed by performing series of experiment-to-code benchmark evaluations [4].…”

Section: Methodsmentioning

confidence: 84%

“…One potential strategy for the US fuel cycle would be to make use of fuel loadings containing high concentrations of transuranic (TRU) nuclides in the next generation reactors [1,3]. The use of such fuels would not only increase fuel supply but could also potentially facilitate prolonged operation modes (via fertile additives) on a single fuel loading [4,5].…”

Section: Introductionmentioning

confidence: 99%

“…Under certain spectral conditions, TRUs/MAs would be able to contribute to a core neutron balance compensating for depletion. The resulting self-stabilization of advanced actinide fuels is expected to prolong operation on a single fuel loading up to lifetimes limited by structural/integrity characteristics [4]. With spectrum shifting, there is a possibility to use VHTRs in waste management.…”

Section: Introductionmentioning

confidence: 99%

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Physics Features of TRU‐Fueled VHTRs

Lewis

Tsvetkov

2009

Science and Technology of Nuclear Installations

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The current waste management strategy for spent nuclear fuel (SNF) mandated by the US Congress is the disposal of high-level waste (HLW) in a geological repository at Yucca Mountain. Ongoing efforts on closed-fuel cycle options and difficulties in opening and safeguarding such a repository have led to investigations of alternative waste management strategies. One potential strategy for the US fuel cycle would be to make use of fuel loadings containing high concentrations of transuranic (TRU) nuclides in the next-generation reactors. The use of such fuels would not only increase fuel supply but could also potentially facilitate prolonged operation modes (via fertile additives) on a single fuel loading. The idea is to approach autonomous operation on a single fuel loading that would allow marketing power units as nuclear batteries for worldwide deployment. Studies have already shown that high-temperature gas-cooled reactors (HTGRs) and their Generation IV (GEN IV) extensions, very-high-temperature reactors (VHTRs), have encouraging performance characteristics. This paper is focused on possible physics features of TRU-fueled VHTRs. One of the objectives of a 3-year U.S. DOE NERI project was to show that TRU-fueled VHTRs have the possibility of prolonged operation on a single fuel loading. A 3D temperature distribution was developed based on conceivable operation conditions of the 600 MWth VHTR design. Results of extensive criticality and depletion calculations with varying fuel loadings showed that VHTRs are capable for autonomous operation and HLW waste reduction when loaded with TRU fuel.

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The neutronics effect of TRISO duplex fuel packing fractions and their comparison with homogeneous thorium‐uranium fuel

Rabir

Ismail

Yahya

2022

Intl J of Energy Research

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Spectrum shifting as a mechanism to improve performance of VHTRs with advanced actinide fuels

Cited by 8 publications

References 6 publications

A neutronic investigation of tristructural isotropic‐duplex fuel in a high‐temperature reactor prismatic seed‐and‐blanket fuel block configuration with reduced power peaking

A neutronic investigation of tristructural isotropic‐duplex fuel in a high‐temperature reactor prismatic seed‐and‐blanket fuel block configuration with reduced power peaking

Physics Features of TRU‐Fueled VHTRs

The neutronics effect of TRISO duplex fuel packing fractions and their comparison with homogeneous thorium‐uranium fuel

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