A summary of sodium-cooled fast reactor development

Aoto, Kazumi; Dufour, Philippe; Yang, Hairui; Glatz, Jean Paul; Kim, Yeong-il; Ashurko, Yury; Hill, R. N.; Uto, Nariaki

doi:10.1016/j.pnucene.2014.05.008

Cited by 164 publications

(38 citation statements)

References 1 publication

Supporting

Mentioning

Contrasting

Unclassified

Order By: Relevance

“…Hence the generated wastes are conventionally immobilized into borosilicate glass framework for a very long time. However for advanced reactors like molten salt reactor, which is one of most suitable next generation reactors, has huge potential to overcome the solid fuel based reactor related problems by using molten thorium fluoride and can also capable of using the vast reserve of thorium present in India for power production, the wastes are not suitable to immobilize in borosilicate glass matrixes. This is due to the fact that boron and silicon containing glasses are highly unstable in presence of fluoride ion sources, which lead to the formation of highly stable compounds like boron tri fluoride (BF 3 ) and silicon tetra fluoride (SiF 4 ).…”

Section: Introductionmentioning

confidence: 99%

Investigating Cationic Distribution, Defect Structure and Phosphor Characteristics of Na₂Sm₂Ca₆(PO₄)₆F₂

et al. 2019

View full text Add to dashboard Cite

Sm3+ based fluorapatite matrix viz. Na2Sm2Ca6(PO4)6F2 was synthesized and characterized by X‐ray diffraction technique, infrared spectroscopy, EDX elemental mapping. Thermal stability was checked by differential thermal analysis technique. Presence of oxygen vacancy related defect centers were confirmed by EPR study, which create several electronic states inside the band gap of the material and give rise to photoemission in the blue and green region in the PL spectra. From the characteristics emission of Sm3+ and its decay profile, it has been confirmed that Sm3+ ion prefers to occupy the less crowdedM2 A site where Ca2+ ion is having 7‐co‐ordination and a direct linking to F− atom.PL decay study also showed that there are two different kinds of oxygen vacancies namely F and F+ center. Finally, based on calculation of International Commission on Illumination (CIE) color coordinates, it has been observed that the compound is a white light emitting material, which has several advantages over the other white light emitting source being a single phase compound.

show abstract

Section: Introductionmentioning

confidence: 99%

Investigating Cationic Distribution, Defect Structure and Phosphor Characteristics of Na₂Sm₂Ca₆(PO₄)₆F₂

et al. 2019

View full text Add to dashboard Cite

show abstract

“…Several advanced SFR concepts (such as ASTRID, JSFR, PRISM, PGSFR, BN-1200, and CFR-600) are under development in a new phase of fast reactors (FRs) design [1]. The concept of SFR has been selected by the Generation IV International Forum (GIF) as a promising nuclear energy system able to fulfill the Generation IV criteria: enhanced safety, economic competitiveness, reduction in environmental burden, and efficient utilization of resources as well as proliferation resistance and enhanced physical protection [2].…”

Section: Introductionmentioning

confidence: 99%

Preliminary Selection of Device Materials to Locally Transform Thermal into SFR Neutron Spectrum

Chrysanthopoulou

Savva

Varvayanni

et al. 2018

Science and Technology of Nuclear Installations

View full text Add to dashboard Cite

The safe introduction of Generation IV (Gen IV) reactor concepts into operation will require extensive testing of their components. This must be performed under neutronic conditions representative of those expected to prevail inside the new reactor cores when in operation. In a thermal Material Testing Reactor (MTR) such neutronic conditions can be achieved by tailoring the prevailing neutron spectrum with the utilization of a device containing appropriate materials. In this work various materials are investigated as candidate components of a device that will be required in case that a thermal MTR neutron energy spectrum must be locally transformed, so as to imitate Sodium cooled Fast Reactor (SFR). Many nuclides have been examined with respect to only their neutronic behavior, providing thus a pool of neutronically appropriate materials for consideration in further investigation, such as regarding reactor safety and fabrication issues. The nuclides have been studied using the neutronics code TRIPOLI-4.8 while the reflector of the Jules Horowitz Reactor (JHR) was considered as the hosting environment of the transforming device. The results obtained suggest that elements with important inelastic neutron scattering could be chosen at a first level as being able to modify the prevailing neutron spectrum towards the desired direction. The factors which are important for an effective inelastic scatterer comprise density and inelastic microscopic cross section, as well as the energy ranges where inelastic scattering occurs. All the above factors have been separately examined in order to suggest potential device materials, able to locally produce SFR neutron spectrum imitation in a thermal MTR.

show abstract

“…Among the six selected systems within the Gen-IV program is a sodiumcooled fast reactor (SFR). It is expected to become available for commercial introduction in around 2030 [2]. In Korea, the R&D on a SFR began in 1997, as one of the national long-term nuclear R&D programs.…”

Section: Introductionmentioning

confidence: 99%

“…As the fuel for a prototype SFR, a metallic fuel, U-Zr alloy, was selected and is being developed. In addition, international collaborative research is also under way on U-TRU-Zr fuel developments with the closed fuel cycle of the full actinide recycling, within the Advanced Fuel Project for the international generation IV (Gen-IV) SFR [2,3]. For the fabrication of SFR metallic fuel rods, the end plug welding is a crucial process [4,5].…”

Section: Introductionmentioning

confidence: 99%

Development of End Plug Welding Technique for SFR Fuel Rod Fabrication

Lee

Kim

et al. 2016

Science and Technology of Nuclear Installations

View full text Add to dashboard Cite

In Korea, R&D on a sodium-cooled fast reactor (SFR) was begun in 1997, as one of the national long-term nuclear R&D programs. As one fuel option for a prototype SFR, a metallic fuel, U-Zr alloy fuel, was selected and is currently being developed. For the fabrication of SFR metallic fuel rods, the end plug welding is a crucial process. The sealing of the end plug to the cladding tube should be hermetically perfect to prevent a leakage of fission gases and to maintain a good reactor performance. In this study, the welding technique, welding equipment, welding conditions, and parameters were developed for the end plug welding of SFR metallic fuel rods. A gas tungsten arc welding (GTAW) technique was adopted and the welding joint design was developed. In addition, the optimal welding conditions and parameters were established. Based on the establishment of the welding conditions, the GTAW technique was qualified for the end plug welding of SFR metallic fuel rods.

show abstract

A summary of sodium-cooled fast reactor development

Cited by 164 publications

References 1 publication

Investigating Cationic Distribution, Defect Structure and Phosphor Characteristics of Na₂Sm₂Ca₆(PO₄)₆F₂

Investigating Cationic Distribution, Defect Structure and Phosphor Characteristics of Na₂Sm₂Ca₆(PO₄)₆F₂

Preliminary Selection of Device Materials to Locally Transform Thermal into SFR Neutron Spectrum

Development of End Plug Welding Technique for SFR Fuel Rod Fabrication

Contact Info

Product

Resources

About

A summary of sodium-cooled fast reactor development

Cited by 164 publications

References 1 publication

Investigating Cationic Distribution, Defect Structure and Phosphor Characteristics of Na2Sm2Ca6(PO4)6F2

Investigating Cationic Distribution, Defect Structure and Phosphor Characteristics of Na2Sm2Ca6(PO4)6F2

Preliminary Selection of Device Materials to Locally Transform Thermal into SFR Neutron Spectrum

Development of End Plug Welding Technique for SFR Fuel Rod Fabrication

Contact Info

Product

Resources

About

Investigating Cationic Distribution, Defect Structure and Phosphor Characteristics of Na₂Sm₂Ca₆(PO₄)₆F₂

Investigating Cationic Distribution, Defect Structure and Phosphor Characteristics of Na₂Sm₂Ca₆(PO₄)₆F₂