Assessment of the possibility of irradiating tungsten and Cu-alloys in IFMIF-DONES using a realistic specimens configuration

被引:0
作者
Alvarez, Irene [1 ]
Anguiano, Marta [1 ]
Mota, Fernando [2 ]
Hernandez, Rebeca [3 ]
Sosa, David [2 ]
Moro, Fabio [4 ]
Noce, Simone [4 ]
Qiu, Yuefeng [5 ]
Park, Jin Hun [5 ]
Arbeiter, Frederik [5 ]
Palermo, Iole [2 ]
机构
[1] Univ Granada, Dept Atom Mol & Nucl Phys, Granada, Spain
[2] CIEMAT, Lab Nacl Fus Confinamiento Magnet, Madrid, Spain
[3] CIEMAT, Div Mat Interes Energet, Madrid, Spain
[4] ENEA Frascati, Nucl Dept, Rome, Italy
[5] Karlsruhe Inst Technol KIT, Karlsruhe, Germany
关键词
IFMIF-DONES; neutronics; comparative; DEMO; DPA; gas-production; MICROSTRUCTURE; DISPLACEMENT;
D O I
10.1088/1741-4326/ada6da
中图分类号
O35 [流体力学]; O53 [等离子体物理学];
学科分类号
070204 ; 080103 ; 080704 ;
摘要
IFMIF-DONES (International Fusion Materials Irradiation Facility-DEMO Oriented NEutron Source) is a facility whose purpose is to obtain data on materials by irradiating them under conditions equivalent to those of the DEMO (DEMOstration) fusion reactor. Tungsten and CuCrZr alloy are two candidate materials to be used in DEMO, tungsten for the first wall and divertor (DIV) and CuCrZr alloy for the DIV. So, studying the behavior of these materials in IFMIF-DONES facility and comparing the results with the DEMO environment is crucial. In the high flux test module in IFMIF-DONES has been considered a realistic distribution of specimens. The IFMIF-EVEDA beam have been used with a footprint size of 20 x 5 cm2, the nominal energy is 40 MeV with a current of 125 mA, for the calculation other energies have been considered 25, 30 and 35 MeV. The results of IFMIF-DONES have been compared with different DEMO concepts, Dual Coolant Lithium Lead, Water Cooled Lithium Lead and Helium Cooled Pebble Bed. In general, the primary displacement damage rate meets between IFMIF-DONES and DEMO, while the gas production is at the limit for W and fulfilled for the CuCrZr alloy.
引用
收藏
页数:10
相关论文
共 34 条
[1]   Neutronic assessment of the IFMIF-DONES HFTM specimen stack distribution [J].
Alvarez, I. ;
Anguiano, M. ;
Mota, F. ;
Hernandez, R. ;
Qiu, Y. .
FUSION ENGINEERING AND DESIGN, 2024, 200
[2]   Development and validation status of the IFMIF High Flux Test Module [J].
Arbeiter, Frederik ;
Abou-Sena, Ali ;
Chen, Yuming ;
Dolensky, Bernhard ;
Heupel, Tobias ;
Klein, Christine ;
Scheel, Nicola ;
Schlindwein, Georg .
FUSION ENGINEERING AND DESIGN, 2011, 86 (6-8) :607-610
[3]   The DEMO Water-Cooled Lead-Lithium Breeding Blanket: Design Status at the End of the Pre-Conceptual Design Phase [J].
Arena, Pietro ;
Del Nevo, Alessandro ;
Moro, Fabio ;
Noce, Simone ;
Mozzillo, Rocco ;
Imbriani, Vito ;
Giannetti, Fabio ;
Edemetti, Francesco ;
Froio, Antonio ;
Savoldi, Laura ;
Siriano, Simone ;
Tassone, Alessandro ;
Roca Urgorri, Fernando ;
Di Maio, Pietro Alessandro ;
Catanzaro, Ilenia ;
Bongiovi, Gaetano .
APPLIED SCIENCES-BASEL, 2021, 11 (24)
[4]   Specification of CuCrZr alloy properties after various thermo-mechanical treatments and design allowables including neutron irradiation effects [J].
Barabash, V. R. ;
Kalinin, G. M. ;
Fabritsiev, S. A. ;
Zinkle, S. J. .
JOURNAL OF NUCLEAR MATERIALS, 2011, 417 (1-3) :904-907
[5]   Towards the EU fusion-oriented neutron source: The preliminary engineering design of IFMIF-DONES [J].
Bernardi, D. ;
Arbeiter, F. ;
Cappelli, M. ;
Fischer, U. ;
Garcia, A. ;
Heidinger, R. ;
Krolas, W. ;
Martin-Fuertes, F. ;
Micciche, G. ;
Munoz, A. ;
Nitti, F. S. ;
Perez, M. ;
Firma, T. ;
Tian, K. ;
Ibarra, A. .
FUSION ENGINEERING AND DESIGN, 2019, 146 :261-268
[6]   Manufacture of thick VPS W coatings on relatively large CuZrCr substrate and its steady high heat load performance [J].
Deng Chunming ;
Liu Min ;
Yang Zhenxiao ;
Deng Changguang ;
Zhou Kesong ;
Kuang Ziqi ;
Zhang Jifu .
JOURNAL OF NUCLEAR MATERIALS, 2014, 455 (1-3) :145-150
[7]   Effect of irradiation temperature and dose on mechanical properties and fracture characteristics of Cu//SS joints for ITER [J].
Fabritsiev, S. A. ;
Pokrovsky, A. S. ;
Peacock, A. ;
Roedig, M. ;
Linke, J. ;
Gervash, A. A. ;
Barabash, V. R. .
JOURNAL OF NUCLEAR MATERIALS, 2009, 386-88 :824-829
[8]   Evaluation of copper alloys for fusion reactor divertor and first wall components [J].
Fabritsiev, SA ;
Zinkle, SJ ;
Singh, BN .
JOURNAL OF NUCLEAR MATERIALS, 1996, 233 :127-137
[9]   Alternatives for upgrading the EU DCLL breeding blanket from MMS to SMS [J].
Fernandez-Berceruelo, Ivan ;
Palermo, Iole ;
Urgorri, Fernando R. ;
Garcia, Angela ;
Rapisarda, David ;
Moya, Luis ;
Rueda, Fernando ;
Alonso, David ;
Ibarra, Angel .
FUSION ENGINEERING AND DESIGN, 2021, 167
[10]  
Fischer U., 2020, EUROfusion IDM EFDA2MM3A6 v1.2