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

Deng, Nianbiao; Yu, Tao; Xie, Jinsen; Chen, Zhenping; Xie, Qingming; Zhao, Pengcheng; Zijing, Liu; Zeng, Wenjie

doi:10.1016/j.net.2018.10.022

Cited by 11 publications

(2 citation statements)

References 4 publications

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“…The CR is defined as the ratio of fissile atom production to fissile atom consumption, while the FIR is calculated as a ratio of instantaneous fissile nuclide inventory to initial fissile nuclide inventory. The fissile inventory in both calculations also included 239 Np (Figure 12C,D) and 233 Pa (Figure 13C,D) due to their relatively fast conversion into 239 Pu and 233 U via beta decay 25,62,63 …”

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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“…With the development of nuclear energy, the utilization of thorium has been discussed in various types of reactors with varying intensity, particularly in pressurized water reactors (PWRs), boiling water reactors, heavy water reactors, Canadian deuterium natural uranium reactors, molten salt reactors (MSRs), hybrid systems, accelerator‐driven systems, high temperature reactors (HTRs), breeder reactors, as well as in fast reactors . Thorium has gained considerable amount of interest because of its many advantages that;characterize it as fuel.…”

Section: Introductionmentioning

confidence: 99%

Comparison of homogeneous and heterogeneous thorium fuel blocks with four drivers in advanced high temperature reactors

et al. 2020

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Thorium is an attractive potential fuel owing to its abundance and unique thermal, neutronic, and chemical properties. One way to utilize thorium in block-type advanced high temperature reactors (AHTRs) is to homogenously mix the driver fuel (eg, U-233) with thorium in every fuel kernel of the tristructural-isotropic particles in a fuel block, which is the mixed oxide fuel (MOX) concept. Application of the seed and blanket (S&B) concept, that is, driver fuel in the seed region of a fuel block and thorium in the blanket region, is also another method to utilize thorium. To investigate the differences in the utilization of thorium using the MOX and S&B concepts in AHTRs, their multiplication factors (k ∞ ), discharge burnups, conversion ratios, and reactivity temperature coefficients are compared. The investigated drivers include U-233 (U3), weapons-grade uranium (WU), weapons-grade plutonium (WPu), and reactor-grade plutonium (RPu). The results demonstrate that the MOX block with plutonium drivers has a higher discharge burnup in comparison with the S&B block. When the heavy metal mass is 6 kg and the initial mass of the fissile materials is 0.65 kg per block, the MOX block achieves 27% higher discharge burnup than the S&B block with the RPu driver. In contrast, the S&B block achieves higher discharge burnup in the case of uranium drivers (U3 and WU). The MOX block achieves a higher conversion ratio for all the drivers. Furthermore, the MOX block achieves a stronger negative moderator temperature coefficient of reactivity than the S&B block for all the driver fuels.

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Simulation and experimental verification for Rh-SPND burnup effect

Wu,

Luo,

Cai

et al. 2024

Annals of Nuclear Energy

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

Cited by 11 publications

References 4 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

Comparison of homogeneous and heterogeneous thorium fuel blocks with four drivers in advanced high temperature reactors

Simulation and experimental verification for Rh-SPND burnup effect

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