Optimization of seed-blanket type fuel assembly for reduced-moderation water reactor

Shelley, Afroza; Shimada, Shoichiro; Kugo, Teruhiko; Ōkubo, Tsutomu; Iwamura, Takamichi

doi:10.1016/s0029-5493(03)00107-9

Cited by 16 publications

(4 citation statements)

References 3 publications

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“…A PWR-type reduced moderation water reactor with seed-blanket type FAs achieved a conversion ratio of 0.97 with a void coefficient of 20.81 pcm/%void and 45 GWd/t (Shelley et al 2003). Tight lattice fuel assemblies (FAs) with a narrow gap between the fuel rods were adopted, but a high enough breeding ratio to meet the growth rate of energy demand has not been successfully achieved.…”

Section: Breeder Reactormentioning

confidence: 99%

Supercritical-Pressure Light Water Cooled Reactors

Oka

Mori

2014

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Section: Breeder Reactormentioning

confidence: 99%

Supercritical-Pressure Light Water Cooled Reactors

Oka

Mori

2014

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“…Tight lattice fuel assemblies (FA) with narrow gap between the fuel rods were adopted, but high breeding ratio meeting the growth rate of energy demand has not been achieved successfully. A PWR-type reduced moderation water reactor with seed-blanket type FA achieved the conversion ratio of 0.97 with the void coefficient of þ20.81pcm/%void and 45GWd/t [1].…”

Section: Introductionmentioning

confidence: 99%

Plutonium breeding of light water cooled fast reactors

Oka

Inoue

Yoshida

2013

Journal of Nuclear Science and Technology

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Light water cooled fast reactor with new fuel assemblies (FA) has been studied for high breeding of fissile plutonium. It achieves fissile plutonium surviving ratio (FPSR) of 1.342 (discharge/loading), 1.013 end and beginning of equilibrium cycle (EOEC/BOEC), and compound system doubling time (CSDT) of 95.9 years at the average coolant density of pressurized water reactor (PWR). It is further improved for reduced moderation boiling water reactor (BWR) (RMWR) coolant density. Fissile plutonium surviving ratio reaches 1.397 (discharge/loading), 1.030 (EOEC/BOEC) and CSDT is 37 years. The present study has shown the possibility of breeding at the PWR coolant density and meeting the growth rate of energy demand of advanced countries at the RMWR and Super FR coolant density for the first time. The new FA consist of closely packed fuel rods. The integrity of welding of fuel rods at the top and bottom ends is maintained as the conventional fuel rods. The coolant to fuel volume fraction is reduced to 0.085, onesixth of that of RMWR. The volume fraction remains unchanged with the diameter of the fuel rod. The thermal hydraulic design of the cores remains for the future study.

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“…For example, 'Advanced Pressurized Water Reactor' [3], 'Supercritical Water-Cooled Reactor' [4][5][6], 'High Performance Light Water Reactor' [7], 'Reduced Moderation Water Reactor' [8], and 'Innovative Water Reactor for Flexible Fuel Cycle' [9]. In addition, some liquid metal reactors, including ones ever in operation and test facilities, also applied tight lattice for fuel assembly design [10][11][12].…”

Section: Introductionmentioning

confidence: 99%

“…The tight lattice concept, which often refers to a rod bundle with relatively small p / d , is employed in some innovative designs of advanced or new‐generation reactors. For example, ‘Advanced Pressurized Water Reactor’ , ‘Supercritical Water‐Cooled Reactor’ , ‘High Performance Light Water Reactor’ , ‘Reduced Moderation Water Reactor’ , and ‘Innovative Water Reactor for Flexible Fuel Cycle’ . In addition, some liquid metal reactors, including ones ever in operation and test facilities, also applied tight lattice for fuel assembly design .…”

Section: Introductionmentioning

confidence: 99%

A circumferentially non-uniform fuel model and its application to thermal-hydraulic code

Yang

Liu

2017

Int J Energy Res

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SUMMARYIn the fuel assemblies in reactor core, the distribution of temperature is not uniform in the fuel rod along the circumferential direction. The circumferential temperature difference could be neglected for conventional assembly design but increases significantly in a tight lattice.To investigate the circumferential non-uniformity of heat transfer in rod bundles, this paper firstly establishes mathematical model and makes theoretical analyses, based on which influential non-dimensional numbers are summarized. Then, a semi-empirical correlation describing this phenomenon is proposed based on theoretical results and CFD sensitivity analyses. Finally, a three-dimensional model for cylindrical fuel is introduced in the thermal-hydraulic code to predict circumferential heat transfer non-uniformity in different geometry and flow conditions. To validate this model, some results are compared with experimental data of bundle test for subcritical and supercritical water.The three-dimensional fuel model for sub-channel code is a new numerical tool to predict the peak cladding and fuel temperature and can be applied in thermal-hydraulic analysis of fuel assemblies of tight lattice design.

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Optimization of seed-blanket type fuel assembly for reduced-moderation water reactor

Cited by 16 publications

References 3 publications

Supercritical-Pressure Light Water Cooled Reactors

Supercritical-Pressure Light Water Cooled Reactors

Plutonium breeding of light water cooled fast reactors

A circumferentially non-uniform fuel model and its application to thermal-hydraulic code

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