Assessment of the shielding efficiency of the HCLL blanket for a DEMO-type fusion reactor

J. Jordanova (1) , J.-F. Salavy (2) , U. Fischer (3) , P. Pereslavtsev (3) , Y. Poitevin (4) , A. Li Puma (2) , N. Nikolova-Todorova (5)

1 INRNE - Institute For Nuclear Research and Nuclear Energy
2 CEA-DES (ex-DEN) - CEA-Direction des Energies (ex-Direction de l'Energie Nucléaire)
3 Forschungszentrum Karlsruhe
4 EFDA-CSU - European Fusion Development Agreement [Garching bei München]
5 Shumen University [Schumen]

This work summarizes the results of a neutronic study on the HCLL blanket for a DEMO-type fusion reactor. The analysis is based on three-dimensional Monte Carlo calculations using the MCNP-4C code. It comprises the assessment of the shielding efficiency in terms of the radiation loads to the superconducting TF-coils and the neutron induced production of He and H gas in the steel structure of the blanket and at locations where the welding of pipe connections is assumed. The analysis is performed utilizing three-dimensional 9$^0$-sector model representing the modular HCLL breeder blanket developed by CEA. The shielding performance of the blanket/shield/vacuum vessel system is assessed at the torus mid-plane considering three variants of a two-component shield, arranged in between the central inboard modules and the Vacuum Vessel. Estimates of radial distributions of the He and H gas production in the steel structure of the blanket are obtained and the radial depth where the re-weldability criterion for the He production <1 appm is fulfilled is identified.

Mots clés: HCLL; DEMO reactor; Shielding performance; Epoxy insulator; He and H production

Domaines: Physique Nucléaire Expérimentale [nucl-ex]

J. Jordanova, J.-F. Salavy, U. Fischer, P. Pereslavtsev, Y. Poitevin, et al.. Assessment of the shielding efficiency of the HCLL blanket for a DEMO-type fusion reactor. FEC2006 - Fusion Energy Conference 2006, Oct 2006, Chengdu, China. ⟨cea-02513449⟩