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IRIS
A new Deuterium-Tritium campaign (DTE2) is planned at JET in the next years, with a proposed 14MeV neutron budget of 1.7×1021, which is nearly an order of magnitude higher than any previous DT campaigns. The neutron and gamma ray fields inside the JET device during DT plasma operations at specific locations have previously been evaluated. It is estimated that a total neutron fluence on the first wall of JET of up to 1020 n/m2 could be achieved, which is comparable to the fluence occurring in ITER at the end of life in the rear part of the port plug, where several diagnostic components will be located.The purpose of the present work is to evaluate the radiation damage and nuclear heating in selected functional materials to be irradiated at JET during DT plasma operation. These quantities are calculated with the use of the MCNP6 code and the FISPACT II code. In particular the neutron and gamma ray fields at specific locations inside the JET device, dedicated to material damage studies, were characterized. The emphasis is on a potential long term irradiation station located close to the first wall at outboard midplane, offering the opportunity to irradiate samples of functional materials used in ITER diagnostics, to assess the degradation of the physical properties. The radiation damage and the nuclear heating were calculated for selected materials irradiated in these positions and for the neutron flux and fluence expected in DTE2. The studied candidate functional materials include, among others, Sapphire, YAG, ZnS, Spinel, Diamond. In addition the activation of the internal irradiation holder itself was calculated with FISPACT. Damage levels in the range of 10-5 dpa were found.
Radiation damage and nuclear heating studies in selected functional materials during the JET DT campaign
Lengar, Igor;Čufar, Aljaž;Conroy, Sean;Batistoni, Paola;Popovichev, Sergey;Snoj, Luka;Syme, Brian;Vila, Rafael;Stankunas, Gediminas;Abhangi, M.;Abreu, P.;Aftanas, M.;Afzal, M.;Aggarwal, K. M.;Aho Mantila, L.;Ahonen, E.;Aints, M.;Airila, M.;Albanese, R.;Alegre, D.;Alessi, E.;Aleynikov, P.;Alfier, A.;Alkseev, A.;Allan, P.;Almaviva, S.;Alonso, A.;Alper, B.;Alsworth, I.;Alves, D.;Ambrosino, G.;Ambrosino, R.;Amosov, V.;Andersson, F.;Andersson Sunde´n, E.;Angelone, M.;Anghel, A.;Anghel, M.;Angioni, C.;Appel, L.;Apruzzese, G.;Arena, P.;Ariola, M.;Arnichand, H.;Arnoux, G.;Arshad, S.;Ash, A.;Asp, E.;Asunta, O.;Cooper, D.;Cooper, S. R.;Corre, Y.;Corrigan, G.;Cortes, S.;Coster, D.;Couchman, A. S.;Cox, M.;Cox, M. P.;Cox, P.;Craciunescu, T.;Cramp, S.;Crisanti, F.;Cristescu, I.;Croci, G.;Croft, O.;Crombe, K.;Crowe, R.;Cruz, N.;Cseh, G.;Cull, K.;Cupido, L.;Curran, D.;Curuia, M.;Czarnecka, A.;Czarski, T.;Dalley, S.;Dalziel, A.;Darrow, D.;Davies, R.;Davis, W.;Day, C.;Day, I. E.;de la Cal, E.;de la Luna, E.;De Magistris, M.;de Pablos, J. L.;De Tommasi, G.;de Vries, P. C.;Deakin, K.;Deane, J.;Decker, J.;Degli Agostini, F.;Dejarnac, R.;Delabie, E.;den Harder, N.;Dendy, R. O.;Denner, P.;Devaux, S.;Devynck, P.;Di Maio, F.;Di Pace, L.;Dittmar, T.;Dodt, D.;Donne, T.;Dooley, P.;Dorling, S. E.;Dormido Canto, S.;Doswon, S.;Douai, D.;Doyle, P. T.;Dreischuh, T.;Drewelow, P.;Drozdov, V.;Drozdowicz, K.;Dumont, R.;Dumortier, P.;Atanasiu, C. V.;Austin, Y.;Avotina, L.;Axton, M. D.;Dunai, D.;Dunne, M.;Dˇuran, I.;Durodie, F.;Ayres, C.;Bachmann, C.;Baciero, A.;Baia˜o, D.;Bailescu, V.;Baiocchi, B.;Baker, A.;Baker, R. A.;Balboa, I.;Balden, M.;Balshaw, N.;Bament, R.;Banks, J. W.;Baranov, Y. F.;Barlow, I. L.;Barnard, M. A.;Barnes, D.;Barnsley, R.;Baron Wiechec, A.;Baruzzo, M.;Basiuk, V.;Bassan, M.;Bastow, R.;Batista, A.;Batistoni, P.;Bauer, R.;Bauvir, B.;Bazylev, B.;Beal, J.;Beaumont, P. 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2016-01-01
Abstract
A new Deuterium-Tritium campaign (DTE2) is planned at JET in the next years, with a proposed 14MeV neutron budget of 1.7×1021, which is nearly an order of magnitude higher than any previous DT campaigns. The neutron and gamma ray fields inside the JET device during DT plasma operations at specific locations have previously been evaluated. It is estimated that a total neutron fluence on the first wall of JET of up to 1020 n/m2 could be achieved, which is comparable to the fluence occurring in ITER at the end of life in the rear part of the port plug, where several diagnostic components will be located.The purpose of the present work is to evaluate the radiation damage and nuclear heating in selected functional materials to be irradiated at JET during DT plasma operation. These quantities are calculated with the use of the MCNP6 code and the FISPACT II code. In particular the neutron and gamma ray fields at specific locations inside the JET device, dedicated to material damage studies, were characterized. The emphasis is on a potential long term irradiation station located close to the first wall at outboard midplane, offering the opportunity to irradiate samples of functional materials used in ITER diagnostics, to assess the degradation of the physical properties. The radiation damage and the nuclear heating were calculated for selected materials irradiated in these positions and for the neutron flux and fluence expected in DTE2. The studied candidate functional materials include, among others, Sapphire, YAG, ZnS, Spinel, Diamond. In addition the activation of the internal irradiation holder itself was calculated with FISPACT. Damage levels in the range of 10-5 dpa were found.
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Utilizza questo identificativo per citare o creare un link a questo documento: https://hdl.handle.net/11563/127072
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simulazione ASN
Il report seguente simula gli indicatori relativi alla propria produzione scientifica in relazione alle soglie ASN 2023-2025 del proprio SC/SSD. Si ricorda che il superamento dei valori soglia (almeno 2 su 3) è requisito necessario ma non sufficiente al conseguimento dell'abilitazione. La simulazione si basa sui dati IRIS e sugli indicatori bibliometrici alla data indicata e non tiene conto di eventuali periodi di congedo obbligatorio, che in sede di domanda ASN danno diritto a incrementi percentuali dei valori. La simulazione può differire dall'esito di un’eventuale domanda ASN sia per errori di catalogazione e/o dati mancanti in IRIS, sia per la variabilità dei dati bibliometrici nel tempo. Si consideri che Anvur calcola i valori degli indicatori all'ultima data utile per la presentazione delle domande.
La presente simulazione è stata realizzata sulla base delle specifiche raccolte sul tavolo ER del Focus Group IRIS coordinato dall’Università di Modena e Reggio Emilia e delle regole riportate nel DM 589/2018 e allegata Tabella A. Cineca, l’Università di Modena e Reggio Emilia e il Focus Group IRIS non si assumono alcuna responsabilità in merito all’uso che il diretto interessato o terzi faranno della simulazione. Si specifica inoltre che la simulazione contiene calcoli effettuati con dati e algoritmi di pubblico dominio e deve quindi essere considerata come un mero ausilio al calcolo svolgibile manualmente o con strumenti equivalenti.