This paper presents the main results of the NET-II/ITER first wall stainless steel activation and dose evaluation performed using different activation codes, nuclear cross section data, and data processing techniques. Basic results have been obtained by ANITA activation code. A benchmark exercise has been set up in order to compare nuclear cross section data libraries (AMPX, VITAMIN-C, and VITAMIN-J) and activation codes (ANITA, ORIGEN, and FISPACT-2). The update of the ORIGEN neutron Data Library was obtained by collapsing the 100-group GREAC-ECN-5 Activation Library with the flux-weighted spectrum provided by XSDRNPM-S code; this method allows the radioactivity inventory and the decay heat power evaluations to be done by the ORIGEN-S code. XSDOSE has been used in conjunction with a fixed-source XSDRNPM to evaluate dose rates outside the shield. The ORIGEN-S provides the gamma and neutron source strength and spectra. Various neutron power loads and fluences have been considered. The dose assessment methodology has been checked by comparison of calculated and experimental gamma-dose rate values following non-continuous irradiation of standard fuel elements (U, UO2 natural or slightly enriched) used over a period of 15 years in RB-3 research critical facility, at Montecuccolino, Bologna.

PLASMA FACING COMPONENT ACTIVATION IN NET-II INITIAL D-T PULSED OPERATIONS / Cambi, G.; Cepraga, D. G.; Cavallone, G.; Menapace, E.; Petrizzi, L.; Vanossi, A.; Zucchetti, Massimo. - STAMPA. - 2:(1993), pp. 1306-1310. (Intervento presentato al convegno 17th Symposium On Fusion Technology tenutosi a Roma (Italia) nel 13-18 settembre 1992) [10.1016/B978-0-444-89995-8.50255-1].

PLASMA FACING COMPONENT ACTIVATION IN NET-II INITIAL D-T PULSED OPERATIONS

ZUCCHETTI, MASSIMO
1993

Abstract

This paper presents the main results of the NET-II/ITER first wall stainless steel activation and dose evaluation performed using different activation codes, nuclear cross section data, and data processing techniques. Basic results have been obtained by ANITA activation code. A benchmark exercise has been set up in order to compare nuclear cross section data libraries (AMPX, VITAMIN-C, and VITAMIN-J) and activation codes (ANITA, ORIGEN, and FISPACT-2). The update of the ORIGEN neutron Data Library was obtained by collapsing the 100-group GREAC-ECN-5 Activation Library with the flux-weighted spectrum provided by XSDRNPM-S code; this method allows the radioactivity inventory and the decay heat power evaluations to be done by the ORIGEN-S code. XSDOSE has been used in conjunction with a fixed-source XSDRNPM to evaluate dose rates outside the shield. The ORIGEN-S provides the gamma and neutron source strength and spectra. Various neutron power loads and fluences have been considered. The dose assessment methodology has been checked by comparison of calculated and experimental gamma-dose rate values following non-continuous irradiation of standard fuel elements (U, UO2 natural or slightly enriched) used over a period of 15 years in RB-3 research critical facility, at Montecuccolino, Bologna.
1993
9780444899958
0-444-89995-2
1-4832-9410-2
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Utilizza questo identificativo per citare o creare un link a questo documento: https://hdl.handle.net/11583/2653539
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