Innovative Core Design for Generation IV Sodium-Cooled Fast Reactors

Buiron, L.; Dufour, P; Rimpault, G.; Prulhiere, G.; Thevenot, C.; Tommasi, J.; Varaine, F.; Zaetta, Alain

doi:10.1051/rgn/20074048

Cited by 10 publications

(3 citation statements)

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“…Another method for the enhancement of the leakage in the case of sodium voiding is the replacement of the reflector above the core with a sodium plenum which enhances the leakage significantly in the case of a sodium voiding event in the upper core region. Current publications mostly concentrate on the design of sodium-cooled fast reactor cores [4], on advanced safety concepts for SFR [5], and on basic or detailed discussions on the different influencing parameters on the sodium void coefficient [6,7] and the limited possibilities for enhancing the feedback effects in traditional designs.…”

Section: Introductionmentioning

confidence: 99%

Moderating Material to Compensate the Drawback of High Minor Actinide Containing Transmutation Fuel on the Feedback Effects in SFR Cores

Merk

2013

Science and Technology of Nuclear Installations

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The use of fine distributed moderating material to enhance the feedback effects and to reduce the sodium void effecting SFRs is described. The drawback on the feedback effects due to the introduction of minor actinides into SFR fuel is analyzed. The possibility of compensation of the effect of the minor actinides on the feedback effects by the use of fine distributed moderating material is demonstrated. The consequences of the introduction of fine distributed moderating material into fuel assemblies with fuel configurations foreseen for minor actinide transmutation are analyzed, and the positive effects on the transmutation efficiency are shown. Finally, the possible increase of the Americium content to improve the transmutation efficiency is discussed, the limit value of Americium is determined, and the possibilities given by an increase of the hydrogen content are analyzed.

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Section: Introductionmentioning

confidence: 99%

Moderating Material to Compensate the Drawback of High Minor Actinide Containing Transmutation Fuel on the Feedback Effects in SFR Cores

Merk

2013

Science and Technology of Nuclear Installations

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“…However, the deployment of SFRs at the industrial scale has not started yet. A wide range of designs are still studied [1,2,3,4,5,6,7]. Their technology readiness level are very wide and go from ideas to almost industrial reactors.…”

Section: Introductionmentioning

confidence: 99%

Global and flexible models for Sodium-cooled Fast Reactors in fuel cycle simulations

Ernoult

Doligez

Thiollière

et al. 2019

Annals of Nuclear Energy

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Since Sodium cooled Fast Reactors are present in many scenarios and strategies for the future of nuclear energy while not having a specific design established yet, we created a new fast and flexible model for the dynamic fuel cycle simulation tools CLASS. It includes a depletion meta-model and a fuel loading method based on artificial neural networks. It is able to represent a wide range of Sodium cooled Fast Reactor designs using oxide fuels and a wide range of fuel management strategies within fuel cycle simulation tools. A comprehensive analysis of simplification options has been made in order to choose the right level of complexity for the reference full core depletion calculations performed with the MURE code used for the training of the meta-model. The process from these reference calculations to the final metamodel is explained and a specific focus is given to the operations going from

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“…One important outcome of these full core studies is the development of high leakage cores with their big core diameter (∼5 meters) in combination with a very small core height (≤1 meter). Current publications mostly concentrate on the design of sodium-cooled fast reactor cores [3] and basic or detailed discussions on the different influencing parameters on the sodium void coefficient [4,5] and the limited possibilities for enhancing the feedback effects in traditional designs. Studies concentrating on the reduction of the sodium void effect have been performed in the framework of CP-ESFR project of the European commission by several institutions [5][6][7].…”

Section: Introductionmentioning

confidence: 99%

Fine Distributed Moderating Material with Improved Thermal Stability Applied to Enhance the Feedback Effects in SFR Cores

Merk

2013

Science and Technology of Nuclear Installations

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The use of fine distributed moderating material to enhance the feedback effects and to reduce the sodium void effect in sodium-cooled fast reactor cores is described. The influence of the moderating material on the fuel assembly geometry, the neutron spectrum, the feedback effects, the power and burnup distribution, and the transmutation performance is given. An overview on possible materials is provided and the relationship between hydrogen content and thermal stability is described. A solution for the problem of the limited thermal stability of primarily proposed hydrogen-bearing moderating material ZrH1.6is developed by the use of yttrium-mono-hydride. The similarity in the effects reached by ZrH and YH is demonstrated by comparison calculations. The topic is closed by an overview on material properties, manufacturing issues, experience in fast reactors, and a comparison of raw material costs.

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Innovative Core Design for Generation IV Sodium-Cooled Fast Reactors

Cited by 10 publications

References 0 publications

Moderating Material to Compensate the Drawback of High Minor Actinide Containing Transmutation Fuel on the Feedback Effects in SFR Cores

Moderating Material to Compensate the Drawback of High Minor Actinide Containing Transmutation Fuel on the Feedback Effects in SFR Cores

Global and flexible models for Sodium-cooled Fast Reactors in fuel cycle simulations

Fine Distributed Moderating Material with Improved Thermal Stability Applied to Enhance the Feedback Effects in SFR Cores

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