Comparison of neutronic behavior of UO 2 , (Th- 233 U)O 2 and (Th- 235 U)O 2 fuels in a typical heavy water reactor

Mirvakili, Seyed Mohammad; Kavafshary, Masoomeh Alizadeh; Vaziri, Atiyeh Joze

doi:10.1016/j.net.2014.12.014

Cited by 10 publications

(1 citation statement)

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“…One fascinating solution is the replacement of 238 U, a fertile material currently used in nuclear reactors, with 232 Th [6]. Thorium is a fertile material that can transform into fissile material 233 U upon neutron absorption [7]. In the thermal spectrum, the isotope 233 U has an η-factor (the ratio of neutrons produced from fission reactions to the number of neutrons absorbed) greater than two [8].…”

Section: Introductionmentioning

confidence: 99%

Neutronic design of small modular longlife pressurized water reactor using thorium carbide fuel at a power level of 300–500 MWth

Lapanporo,

Su’ud,

Mustari

2024

EEJET

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This study presents the neutronic design of a small modular longlife Pressurized Water Reactor (PWR) using thorium carbide fuel with 233U fissile material. The target optimization for this study is a reactor designed to operate for 20 years, with excess reactivity throughout the reactor operational cycle consistently below 1.00 % dk/k. The analysis involves dividing the reactor core into three fuel regions with 233U enrichment levels ranging from 3 % to 8 %, with a 1 % difference for each fuel region. To achieve optimum conditions, 231Pa was randomly added to the fuel. The fuel volume fraction in this design varied from 30 % to 65 %, with a 5 % incremental variation. Power level variations are also studied within the 300–500 MWth with increments of 50 MWth. Calculations were performed using the Standard Reactor Analysis Code (SRAC) program with the PIJ and CITATION modules for cell and core calculations utilizing JENDL4.0 nuclide data. Neutronic calculations indicate that the fuel with a 60 % volume fraction achieves optimum conditions at a power level of 300 MWth. The best performance was observed with a fuel volume fraction of 65 %, reaching optimum conditions across power levels ranging from 300 to 500 MWth. For the fuel with the best performance, the power density distributions for low and high power levels follow the same pattern radially and axially. The power peaking factor (PPF) for all fuel configurations approaching the optimum conditions remains below two, a safe limit for the PWR. Other neutronic safety parameters, such as the Doppler coefficient and void fraction coefficient, also stay within the safe limits for the PWR, with both values remaining negative throughout the reactor operational cycle

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Section: Introductionmentioning

confidence: 99%

Neutronic design of small modular longlife pressurized water reactor using thorium carbide fuel at a power level of 300–500 MWth

Lapanporo,

Su’ud,

Mustari

2024

EEJET

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Neutronic feasibility study of (Th-233U)-ZrH1.65 fuel in a modelled TRIGA research reactor

Banni

Kabach

Koua

et al. 2022

Journal of King Saud University - Science

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Automated analysis of grain morphology in TEM images using convolutional neural network with CHAC algorithm

Xu,

Yu,

Chen

et al. 2024

Journal of Nuclear Materials

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Comparison of neutronic behavior of UO 2 , (Th- 233 U)O 2 and (Th- 235 U)O 2 fuels in a typical heavy water reactor

Abstract: Available online xxxKeywords: MCNPX 2.6.0 Neutronic investigation Thorium-based fuel (Th-233 U)O 2 (Th-235 U)O 2 UO 2 a b s t r a c t Background:

Cited by 10 publications

References 11 publications

Neutronic design of small modular longlife pressurized water reactor using thorium carbide fuel at a power level of 300–500 MWth

Neutronic design of small modular longlife pressurized water reactor using thorium carbide fuel at a power level of 300–500 MWth

Neutronic feasibility study of (Th-233U)-ZrH1.65 fuel in a modelled TRIGA research reactor

Automated analysis of grain morphology in TEM images using convolutional neural network with CHAC algorithm

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Comparison of neutronic behavior of UO 2 , (Th- 233 U)O 2 and (Th- 235 U)O 2 fuels in a typical heavy water reactor

Abstract: Available online xxxKeywords: MCNPX 2.6.0 Neutronic investigation Thorium-based fuel (Th-233 U)O 2 (Th-235 U)O 2 UO 2 a b s t r a c t Background:

Cited by 10 publications

References 11 publications

Neutronic design of small modular long­life pressurized water reactor using thorium carbide fuel at a power level of 300–500 MWth

Neutronic design of small modular long­life pressurized water reactor using thorium carbide fuel at a power level of 300–500 MWth

Neutronic feasibility study of (Th-233U)-ZrH1.65 fuel in a modelled TRIGA research reactor

Automated analysis of grain morphology in TEM images using convolutional neural network with CHAC algorithm

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Resources

About

Neutronic design of small modular longlife pressurized water reactor using thorium carbide fuel at a power level of 300–500 MWth

Neutronic design of small modular longlife pressurized water reactor using thorium carbide fuel at a power level of 300–500 MWth