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Nuclear Analysis of the First Wall/Blanket/Shielld of Inertial Fusion Energy Reactors
 

Summary: Nuclear Analysis of the First Wall/Blanket/Shielld of
Inertial Fusion Energy Reactors
Mahmoud Z. Youssef and Mohamed A. Abdou
Mechanical, Aerospace,and Nuclear EngineeringDepartment
University of California. Los Angeles, CA 90024
the Prometheus
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 Li20 B/R/P system. In this paper, the results of the
neutronics parametric study that led to the baseline design of the
EWS 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

  

Source: Abdou, Mohamed - Fusion Science and Technology Center, University of California at Los Angeles

 

Collections: Plasma Physics and Fusion