Conceptual design of compact supercritical water-cooled fast reactor with thermal hydraulic coupling

Yoo, Juhyun; Ishiwatari, Yuki; Oka, Yoshiaki; Liu, Jie

doi:10.1016/j.anucene.2006.07.004

Cited by 53 publications

(26 citation statements)

References 7 publications

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“…The CR of core designed by Yoo et al [15] is 0.696. Thus, the optimized assembly design and reasonable core arrangement significantly improve the CR.…”

Section: Scfr-m Physical Propertiesmentioning

confidence: 99%

“…Yoo et al [15] from Tokyo University had designed a high energy power SCFR core with a negative coolant void coefficient, the seed assemblies and the blanket assemblies are composite arranged in the core. In this study, SCFR-M (supercritical water-cooled fast reactor-mix layout) is designed on the basis of the conceptual design of SCFR which was proposed by Professor OKA.…”

Section: Description Of Scfr Corementioning

confidence: 99%

“…However, the coolant void reactivity coefficient of the core is positive. A tight lattice of the MOX fuel assembly in hexagonal geometry has been proposed with some blanket loaded in SCFR core design [15] [19]. The blanket assembly is to convert fertile nuclide and comprised of depleted UO 2 fuel and ZrH 1.7 layer as solid moderator.…”

Section: Introductionmentioning

confidence: 99%

“…R&D activities are carried out for the past decades. Numbers of conceptual design have been proposed both for thermal spectrum design [3]- [11], and fast spectrum concept [12]- [15].…”

Section: Introductionmentioning

confidence: 99%

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Primary Breeding Ratio Analysis of an Improved Supercritical Water Cooled Fast Reactor

Liu¹,

Xie²,

He³

2015

WJNST

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The purpose of the study is to analyze the breeding ratio of a supercritical water cooled fast reactor (SCFR) and to increase the breeding core of SCFR. The sensitivities of assembly parameters, core arrangements and fuel nuclide components to the breeding ratio are analyzed. In assembly parameters, the seed fuel rod diameter has higher sensitivities to the conversion ratio (CR) than the coolant tube diameter in blanket. Increasing heavy metal fraction is good to CR improvement. The CR of SCFR also increases with a reasonable core arrangement and Pu isotope mass fraction reduction in fuel, which can achieve more negative coolant void reactivity coefficient at the same time. The breeding ratio of SCFR is 1.03128 with a new core arrangement. And the coolant void reactivity coefficient is negative, which achieves a fuel breeding in initial fuel cycle.

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“…The CR of core designed by Yoo et al [15] is 0.696. Thus, the optimized assembly design and reasonable core arrangement significantly improve the CR.…”

Section: Scfr-m Physical Propertiesmentioning

confidence: 99%

Section: Description Of Scfr Corementioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

“…R&D activities are carried out for the past decades. Numbers of conceptual design have been proposed both for thermal spectrum design [3]- [11], and fast spectrum concept [12]- [15].…”

Section: Introductionmentioning

confidence: 99%

See 2 more Smart Citations

Primary Breeding Ratio Analysis of an Improved Supercritical Water Cooled Fast Reactor

Liu¹,

Xie²,

He³

2015

WJNST

View full text Add to dashboard Cite

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“…However, past studies on the core design of the fast spectrum SCWR were mainly based on a two-dimensional R-Z approximation 5,6) or Monte Carlo method. 7) Recently, Yoo et al 8) have developed a three-dimensional neutronics thermal-hydraulic coupled method for the core design of the fast spectrum SCWR. Based on this method, a 1,000 MWe reactor was designed with MOX fuel and stainless steel cladding.…”

Section: Introductionmentioning

confidence: 99%

Fuel, Core Design and Subchannel Analysis of a Superfast Reactor

CAO

Oka

Ishiwatari

et al. 2008

Journal of Nuclear Science and Technology

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A compact supercritical water-cooled fast reactor (superfast reactor) core with a power of 700 MWe is designed by using a three-dimensional neutronics thermal-hydraulic coupled method. The core consists of 126 seed assemblies and 73 blanket assemblies. In the seed assemblies, 251 fuel rods, consisting of MOX pellets, stainless steel (SUS304) cladding, and fission gas plenum are arranged into a tight triangle lattice along with 19 guide tubes for control rods and instrumentation. A zirconium hydride (ZrH) layer is employed in the blanket assemblies to reduce void reactivity. The results of the coupling three-dimensional neutronics and thermal hydraulic calculations show that this core has a high power density of 158.8 W/cm 3 with a maximum linear heat generation rate (MLHGR) less than 39 kW/m, that an average coolant outlet temperature of 500 C is achieved with a maximum cladding surface temperature (MCST) less than 650 C, and that void reactivity coefficients are negative throughout the cycle. Since the thermal-hydraulic part of the core design is based on single-channel analyses, subchannel analyses are also performed on all the seed assemblies to clarify the influence of cross-flow.

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Preliminary study on physical characteristics of single‐pass super‐critical water‐cooled reactor core

et al. 2020

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Summary The super‐critical water‐cooled reactor (SCWR) is one of six types of Gen‐IV reactors. Based on the current mature pressurized water reactor technology, it has several advantages, including high conversion ratio, high breeding of nuclear fuel, high thermal efficiency, and a simplified system. However, due to the combination of water coolant and fast neutron spectrum, there is a need to address safety problems caused by the positive void coefficient. The purpose of this paper is to give a study on physical characteristics for the reactor core. Herein, the core modeling of an SCWR with a single‐pass flow is that seed assemblies and blanket assemblies are arranged in a tornado manner, in which MCNP and SERPENT are used for critical calculation. The assembly design is discussed from the aspects of the thickness of the solid moderator layer and cladding material. Based on the optimized assembly design, UO2, PuO2‐ThO2, and PuO2‐UO2 are selected for the sensitivity analysis of fuel composition. In addition, sensitivity analysis for axial coolant density distribution, water‐to‐fuel volume ratio, reflector thickness and fuel arrangement are carried out. Several fundamental system characteristics are discussed in this paper, including keff, void coefficient, Doppler coefficient, neutron spectrum, power distribution, one‐cycle burnup and conversion ratio. The results help in understanding the design of the SCWR better and provide fundamental research data for further study.

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Conceptual design of compact supercritical water-cooled fast reactor with thermal hydraulic coupling

Cited by 53 publications

References 7 publications

Primary Breeding Ratio Analysis of an Improved Supercritical Water Cooled Fast Reactor

Primary Breeding Ratio Analysis of an Improved Supercritical Water Cooled Fast Reactor

Fuel, Core Design and Subchannel Analysis of a Superfast Reactor

Preliminary study on physical characteristics of single‐pass super‐critical water‐cooled reactor core

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