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Characterization of JET neutron field in irradiation locations for DD, DT and TT plasmas
Culham Sci Ctr, EUROfus Consortium, Abingdon, Oxon, England;Jozef Stefan Inst, Reactor Phys Div, Jamova Cesta 39, Ljubljana, Slovenia.
Culham Sci Ctr, EUROfus Consortium, Abingdon, Oxon, England;Jozef Stefan Inst, Reactor Phys Div, Jamova Cesta 39, Ljubljana, Slovenia.
Culham Sci Ctr, EUROfus Consortium, Abingdon, Oxon, England;ENEA, Fus Tech Unit, Via E Fermi 45, I-00044 Frascati, Italy;Culham Sci Ctr, CCFE, Abingdon OX14 3DB, Oxon, England.
Culham Sci Ctr, EUROfus Consortium, Abingdon, Oxon, England;Culham Sci Ctr, CCFE, Abingdon OX14 3DB, Oxon, England.
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2019 (engelsk)Inngår i: Fusion engineering and design, ISSN 0920-3796, E-ISSN 1873-7196, Vol. 146, s. 1967-1970Artikkel i tidsskrift (Fagfellevurdert) Published
Abstract [en]

The neutron fluxes and spectra were characterized for four locations close to the plasma and related to activation experiments, as the preparation for the upcoming experimental campaigns in JET. The focus was on the study of a variance reduction technique in order to obtain statistically significant results in the parts of the neutron energy spectra, important for irradiation experiments. The DD, DT and TT plasmas were studied with the Monte Carlo hybrid method and the use of the ADVANTG program for generation of weight windows as variance reduction method to accelerate Monte Carlo simulations. The calculations were optimized to obtain low statistical uncertainties for all energy bins in the 640 energy group structure and for all three plasma sources. This included the acceleration of calculations for reaction rates of capture reactions, i.e. in the thermal flux region in irradiation positions on the first wall. Speed-ups due to use of the hybrid method in excess of two orders of magnitude were found with respect to analog calculations despite the vicinity of the plasma source.

sted, utgiver, år, opplag, sider
ELSEVIER SCIENCE SA , 2019. Vol. 146, s. 1967-1970
Emneord [en]
JET, KN2 detector, Long-term irradiation station, Neutron transport calculations, ADVANTG
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Identifikatorer
URN: urn:nbn:se:uu:diva-396639DOI: 10.1016/j.fusengdes.2019.03.078ISI: 000488313700124OAI: oai:DiVA.org:uu-396639DiVA, id: diva2:1368609
Tilgjengelig fra: 2019-11-07 Laget: 2019-11-07 Sist oppdatert: 2019-11-07bibliografisk kontrollert

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