Speaker
Lee Packer
(Nuclear Technology Department)
Description
Activities under the EUROfusion work package (WP) JET3 programme have been established to enable the technological exploitation of the planned JET experiments over the next few years, which culminates in a D-T experimental campaign, DTE-2. In the areas of nuclear technology and nuclear safety the programme offers a unique opportunity to provide experimental data that is relevant to ITER. The key purpose of the collected data will be to support benchmarking and validation activities relating to neutronics and activation codes, and associated nuclear data, that are used to predict the nuclear behavior of ITER component and materials, during and after operations.
This paper details the status and key issues of the ongoing ACT sub-project under WP JET3, which aims to take advantage of the large 14 MeV neutron fluence expected during JET DTE2 to irradiate samples of real ITER materials used in the manufacturing of the main in-vessel tokamak components. The materials considered, with specified minor elemental impurity levels, include: Nb3Sn, SS316L steels from a range of manufacturers, SS304B, Alloy 660, Be, W, CuCrZr, OF-Cu, XM-19, Al bronze, Nb3Sn, NbTi and EUROFER. The activities include provision for measurement of nuclide activities for each material and comparison against the predicted quantities through calculation with the FISPACT-II inventory code. Included here are key pre-analysis results for the selected ITER irradiation samples, and corresponding optimization of diagnostic foils (Ti, Mn, Co, Ni, Y, Fe, Co, Sc, Ta) that will be irradiated at selected positions inside JET irradiation stations in order to determine the neutron spectrum. Preliminary experimental activation results through recent JET DD operations are discussed.
This work has been carried out within the framework of the EUROfusion Consortium and has received funding from the Euratom research and training programme 2014-2018 under grant agreement No 633053 and from the RCUK Energy Programme [EP/I501045].
Co-authors
A. Wojcik-Gargula
(Institute of Nuclear Physics, Polish Academy of Sciences, PL-31-342 Krakow, Poland)
B. Colling
(Nuclear Technology Department, UKAEA, Abingdon, United Kingdom)
D. Leichtle
(Fusion for Energy, Josep Pla 2, Torres Diagonal Litoral B3, 08019, Spain)
E Laszynska
(Institute of Plasma Physics and Laser Microfusion, 01-497 Warsaw, Poland)
I. E. Stamatelatos
(Institute of Nuclear and Radiological Sciences, Athens, 15310, Greece)
J.W. Mietelski
(Institute of Nuclear Physics, Polish Academy of Sciences, PL-31-342 Krakow, Poland)
K. Drozdowicz
(Institute of Nuclear Physics, Polish Academy of Sciences, PL-31-342 Krakow, Poland)
L. W. Morgan
(Nuclear Technology Department, UKAEA, Abingdon, United Kingdom;Nuclear Technology Department, UKAEA, Abingdon, United Kingdom)
Lee Packer
(Nuclear Technology Department, UKAEA, Abingdon, United Kingdom)
M. Pillon
(Department of Fusion and Technology for Nuclear Safety and Security , ENEA, via E. Fermi 45, 00044 Frascati (Rome), Italy)
M. R Gilbert
(Nuclear Technology Department, UKAEA, Abingdon, United Kingdom)
P. Batistoni
(Department of Fusion and Technology for Nuclear Safety and Security , ENEA, via E. Fermi 45, 00044 Frascati (Rome), Italy)
S. Jednorog
(Institute of Plasma Physics and Laser Microfusion, 01-497 Warsaw, Poland)
S. Lilley
(Nuclear Technology Department, UKAEA, Abingdon, United Kingdom)
T. Vasilopoulou
(Institute of Nuclear and Radiological Sciences, Athens, 15310, Greece)
