Adapting an X-Ray/Debris Shield to the Cascade ICF Power Plant: Neutronics Issues
Author:
Affiliation:
1. Lawrence Livermore National Laboratory P.O. Box 5508 L-459 Livermore, CA 94550 (415)-423-1168
Publisher
Informa UK Limited
Subject
General Engineering
Link
https://www.tandfonline.com/doi/pdf/10.13182/FST91-A29423
Reference16 articles.
1. Preventing Vaporization and Destructive Shock Waves in ICF Target-Chamber First Walls
2. ORLIB: a computer code that produces one-energy group, time- and spatially-averaged neutron cross sections
3. FORIG: a computer code for calculating radionuclide generation and depletion in fusion and fission reactors. User's manual
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1. Power generation system using two models for an inertial confinement fusion reactor;Proceedings of the Institution of Mechanical Engineers, Part A: Journal of Power and Energy;2005-08-01
2. Inertial Fusion Energy: A Clearer View of the Environmental and Safety Aspects;Fusion Technology;1998-05
3. Accidental release characteristics of activated materials in inertial and magnetic fusion reactors;Journal of Nuclear Materials;1994-09
4. Computer modeling of ICF target chamber phenomena;Laser and Particle Beams;1994-06
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