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Status of ITER material activation experiments at...
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Status of ITER material activation experiments at JET

Abstract

Activities under the EURO fusion work package 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 bench marking 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 work package JET3, which aims to take advantage of the large 14MeV neutron fluence expected during JET DTE-2 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, W, CuCrZr, OF-Cu, XM-19, Al bronze, 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 dosimetry 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 D–D operations are discussed.

Authors

Packer LW; Batistoni P; Colling B; Drozdowicz K; Jednorog S; Gilbert MR; Laszynska E; Leichtle D; Mietelski JW; Pillon M

Volume

124

Pagination

pp. 1150-1155

Publisher

Elsevier

Publication Date

November 1, 2017

DOI

10.1016/j.fusengdes.2017.01.037

Conference proceedings

Fusion Engineering and Design

ISSN

0920-3796

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