Potential irradiation of Cu alloys and tungsten samples in DONES

Mota, F.; Palermo, Iole; Laces, S.; Mollá, J.; Ibarra, Á.

doi:10.1088/1741-4326/aa8a9b

Cited by 7 publications

(7 citation statements)

References 42 publications

(60 reference statements)

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“…This is due to their good ductility, high thermal and electrical conductivity and high commercial availability. In addition, they exhibit high fracture toughness and high resistance to radiation damage [ 131 ].…”

Section: Ifmif-donesmentioning

confidence: 99%

“…On the CuCrZr side, structural damage rates of 5 to 30 dpa/fpy, a helium production rate of 6–8 appm He/dpa and a hydrogen production rate of 48–50 appm H/dpa can be achieved. Thus, for both W and CuCrZr, the values expected in DEMO are even surpassed [ 131 ].…”

Section: Ifmif-donesmentioning

confidence: 99%

“…The data in Table 5 show that the damage dose rate requirements called for in the fusion roadmap for Cu and tungsten alloys for DONES meet the maximum values calculated in the area of the DEMO divertor with DCLL design. The damage dose rate and the H and He production are analyzed at the different locations and compared with the real irradiation conditions in the FW and divertor [ 131 ].…”

Section: Ifmif-donesmentioning

confidence: 99%

“…These simulations (the experimental results presented were obtained with the McDeLicious code [ 131 ] used for neutron transport calculations) performed for the HFTM ( Figure 25 ) are intended to evaluate whether the tungsten and CuCrZr alloys—planned to be used in the first and second layer of the DEMO divertor, respectively— meet the expected values for a DCLL type concept according to the damage requirements set out in the EUROfusion roadmap. The objective is to evaluate the amount of irradiated volume subjected to a given damage dose rate (dpa/fpy).…”

Section: Ifmif-donesmentioning

confidence: 99%

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Materials to Be Used in Future Magnetic Confinement Fusion Reactors: A Review

Alba¹,

Rodríguez²,

Cerdeira³

2022

Materials

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This paper presents the roadmap of the main materials to be used for ITER and DEMO class reactors as well as an overview of the most relevant innovations that have been made in recent years. The main idea in the EUROfusion development program for the FW (first wall) is the use of low-activation materials. Thus far, several candidates have been proposed: RAFM and ODS steels, SiC/SiC ceramic composites and vanadium alloys. In turn, the most relevant diagnostic systems and PFMs (plasma-facing materials) will be described, all accompanied by the corresponding justification for the selection of the materials as well as their main characteristics. Finally, an outlook will be provided on future material development activities to be carried out during the next phase of the conceptual design for DEMO, which is highly dependent on the success of the IFMIF-DONES facility, whose design, operation and objectives are also described in this paper.

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Section: Ifmif-donesmentioning

confidence: 99%

Section: Ifmif-donesmentioning

confidence: 99%

Section: Ifmif-donesmentioning

confidence: 99%

Section: Ifmif-donesmentioning

confidence: 99%

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Materials to Be Used in Future Magnetic Confinement Fusion Reactors: A Review

Alba¹,

Rodríguez²,

Cerdeira³

2022

Materials

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“…Early generation fusion reactors will operate with modest FW loads. In fact, different types of ferritic martensitic steels are continuing subject of recent works, such as utilizations austenitic SS in Russian studies, 42 reduced activation ferritic martensitic steel, 43 Korean developed ferritic martensitic steel 44 and India‐specific ferritic martensitic steel 45 . Under consideration of all these aspects, SS304 is selected as the FW material in a group of the calculations to be on conservative side.…”

Section: Numerical Calculationsmentioning

confidence: 99%

Study on the fusion reactor performance with different materials and nuclear waste actinides

Şahi̇n

Sahiner

et al. 2020

Int J Energy Res

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Summary In this study, both pure fusion blanket and fusion‐fission (hybrid) reactor blanket performance were investigated and discussed separately in two phases. In the first phase, a Monte Carlo radiation damage analysis has been performed for stainless steel (SS304, SS316, and oxide dispersion strengthened (ODS)), molybdenum, vanadium, and tungsten as the first wall (FW) materials, in combination with selected tritium breeders. The main technical parameters for fusion reactors, such as tritium breeding ratio, fusion energy multiplication factor (M), displacement per atom (DPA), and gas production (He, H) have been evaluated. All numerical calculations have been carried out in spherical geometry with MCNP6 code package using continuous energy cross‐sections from the ENDF/B‐VIII.0 library, except DPA calculations. Instead of the ENDF/B‐VIII.0 library, the 30‐group CLAW‐IV library was employed for DPA calculations. Structural material selection for the FW respect to radiation damage limits and reactor performance for energy production and tritium has been concluded. Conventional thermal reactors, such as light water reactors andCanada Deuterium Uranium (CANDU) reactors are producing substantial quantities of transuranic elements, which represent serious nuisance and permanent hazard potential. On the other hand, they become fissionable material under high energetic fusion neutron irradiation and multiply the fusion energy. In the second phase, the investigations are extended to the incineration of minor actinides (MA) in the fusion‐fission (hybrid) mode. The transmutation history of MA nuclear waste is included. MA are added into the first zone of the coolant in TRi‐structural ISOtropic particle TRISO particles with a volume fraction of 6%. The transformation scenario for all MA by SS 304 steel FW is practically the same as with the ODS FW.

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The thermal conductivity of defected copper at finite temperatures

Pan

2019

J Mater Sci

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Potential irradiation of Cu alloys and tungsten samples in DONES

Abstract: There are some typos found in the isotopic composition in table 2, therefore, the isotopic composition of the Tungsten material used in the calculations has been corrected.

Cited by 7 publications

References 42 publications

Materials to Be Used in Future Magnetic Confinement Fusion Reactors: A Review

Materials to Be Used in Future Magnetic Confinement Fusion Reactors: A Review

Study on the fusion reactor performance with different materials and nuclear waste actinides

The thermal conductivity of defected copper at finite temperatures

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