Title :
Nuclear analysis of the first wall/blanket/shield of the Prometheus inertial fusion energy reactors
Author :
Youssef, Mahmoud Z. ; Abdou, Mohamed A.
Author_Institution :
Dept. of Mech., Aerosp. & Nucl. Eng., California Univ., Los Angeles, CA, USA
Abstract :
The design of the cavity and shielding system of the Prometheus reactors was undertaken by UCLA in conjunction with an IFE conceptual reactor study led by McDonnell Douglas. A wetted wall by a thin lead film was used as part of the first wall system (FWS) designated to protect the cavity against the microexplosions. The FWS is attached to the blanket/reflector/plena (B/R/P) system. For low activation consideration, SiC was used as the structural material and low pressure helium (1.5 MPa) was chosen as the coolant in the Li2O B/R/P system. In this paper, the results of the neutronics parametric study that led to the baseline design of the FWS and B/R/P system are given. The attenuation characteristics of two types of shielding materials were studied, namely, reinforced concrete and low-activation Pb/B4C composite. The latter was chosen as the bulk and beamlines shield due to its low activation
Keywords :
fusion reactor blankets; fusion reactor materials; fusion reactor theory; fusion reactors; shielding; 1.5 MPa; B4C; FWS; IFE conceptual reactor study; Li2O; Li2O B/R/P system; Pb; Prometheus inertial fusion energy reactors; attenuation characteristics; baseline design; blanket; blanket/reflector/plena system; cavity; first wall; first wall system; low activation consideration; low pressure He coolant; low-activation Pb/B4C composite; microexplosions; neutronics parametric study; nuclear analysis; reinforced concrete; shield; structural material; thin lead film; wetted wall; Attenuation; Building materials; Coolants; Helium; Inductors; Lead; Optical films; Parametric study; Protection; Silicon carbide;
Conference_Titel :
Fusion Engineering, 1993., 15th IEEE/NPSS Symposium on
Conference_Location :
Hyannis, MA
Print_ISBN :
0-7803-1412-3
DOI :
10.1109/FUSION.1993.518440
