Activation analysis for ITER design options

Author

Attaya, Homy

Author_Institution

Argonne Nat. Lab., IL, USA

Volume

1

fYear

1995

fDate

30 Sep-5 Oct 1995

Firstpage

369

Abstract

This paper presents a summary of the activation analyses that have been performed for the shielding blanket (SS/water) and for the breeding blanket (Li/V) of ITER design options. The activation code RACC-P, which has been modified for pulsed operation, has been used in these calculations. The spatial distributions of the radioactive inventory, decay heat, biological hazard potential, and the contact dose were calculated for the two designs for different operation modes and targeted fluences. A one-dimensional toroidal cylindrical geometrical model has been utilized to determine the neutron fluxes in the two designs. The results are normalized for an inboard and outboard neutron wall loadings of 0.91 and 1.2 MW/m², respectively

Keywords

dosimetry; fusion reactor blankets; fusion reactor design; fusion reactor operation; fusion reactors; health hazards; neutron activation analysis; neutron flux; nuclear engineering computing; radiation protection; shielding; 1D toroidal cylindrical geometrical model; FeCCr-H₂O; ITER design options; Li-V; RACC-P code; activation analyses; activation code; biological hazard potential; breeding blanket; contact dose; decay heat; neutron flux; operation modes; pulsed operation; radioactive inventory; shielding blanket; spatial distributions; targeted fluences; Activation analysis; Assembly; Biohazards; Biological system modeling; Coolants; Electronic design automation and methodology; Fusion reactor design; Laboratories; Neutrons; Solid modeling;

fLanguage

English

Publisher

ieee

Conference_Titel

Fusion Engineering, 1995. SOFE '95. Seeking a New Energy Era., 16th IEEE/NPSS Symposium

Conference_Location

Champaign, IL

Print_ISBN

0-7803-2969-4

Type

conf

DOI

10.1109/FUSION.1995.534244

Filename

534244