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Physics and technology conditions for attaining tritium self-sufficiency for the DT fuel cycle
Fusion engineering and design, 2006-02, Vol.81 (8), p.1131-1144
2006
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Damage production and accumulation in SiC structures in inertial and magnetic fusion systems
Journal of nuclear materials, 2011-10, Vol.417 (1-3), p.445-450
2011
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An overview of the US DCLL ITER-TBM program
Fusion engineering and design, 2010-12, Vol.85 (7), p.1129-1132
2010
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Three-dimensional nuclear analysis for the US dual coolant lead lithium ITER test blanket module
Fusion engineering and design, 2010-12, Vol.85 (7), p.1027-1032
2010
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Three-dimensional nuclear analysis of the final optics of a laser driven fusion power plant
Fusion engineering and design, 2008-12, Vol.83 (10), p.1879-1883
2008
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Three-dimensional neutronics assessment of dual coolant molten salt blankets with comparison to one-dimensional results
Fusion engineering and design, 2006-02, Vol.81 (1), p.505-511
2006
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Nuclear analyses for two “look-alike” helium-cooled pebble bed test blanket sub-modules proposed by the US for testing in ITER
Fusion engineering and design, 2006-02, Vol.81 (8), p.1567-1576
2006
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The breeding potential of ‘flinabe’ and comparison to ‘flibe’ in ‘CLiFF’ high power density concept
Fusion engineering and design, 2002-11, Vol.61, p.497-503
2002
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Impact of tritium removal and He-3 recycling on structure damage parameters in a D–D fusion system
Fusion engineering and design, 2002-11, Vol.61, p.561-567
2002
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Neutronics features of a high power density first wall/blanket with lithium evaporation cooling
Fusion engineering and design, 2001-05, Vol.55 (1), p.45-53
2001
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Radwaste volume in lithium and Flibe thick liquid wall and comparison to conventional SW concepts
Fusion engineering and design, 2002-12, Vol.63 (64), p.263-269
2002
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Benchmarking a CAD-Based Monte Carlo Code Using Fusion-Specific Experiments
Nuclear technology, 2011-07, Vol.175 (1), p.264-270
2011
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Self-shielding effects in a tungsten layer in a fusion device
Fusion engineering and design, 1999-03, Vol.45 (1), p.65-73
1999
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Experimental validation of calculations of decay heat induced by 14 MeV neutron activation of ITER materials
Fusion engineering and design, 1999-03, Vol.45 (1), p.75-88
1999
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Shielding analysis for a heavy ion beam chamber with plasma channels for ion transport
Fusion engineering and design, 2000-11, Vol.51, p.1137-1142
2000
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Nuclear analysis for a flowing Li2O particulate blanket without structural first wall
Fusion engineering and design, 2000-11, Vol.49-50, p.667-673
2000
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Component lifetime comparison and waste volume in CLiFF Sn/Flibe and Sn/LiPb blankets
Fusion engineering and design, 2002-12, Vol.63, p.277-283
2002
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Shielding analysis for the ITER divertor and vacuum-pumping ducts
Fusion engineering and design, 1995-03, Vol.28 (1-2), p.429-436
1995
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Radiological dose calculations for the particle beam fusion accelerator upgrade (PBFA-U)
Fusion engineering and design, 1995-03, Vol.28 (1-2), p.730-736
1995
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Differences between neutron damage in inertial and magnetic confinement fusion materials test facilities
Journal of nuclear materials, 1985-01, Vol.133, p.52-57
1985
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Neutronics Performance Characteristics of the High Power Density Evolve First Wall/Blanket System
FUSION TECHNOL, 2001-03, Vol.39 (2P2), p.793-797
2001
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Nuclear analysis for the inertially confined direct drive laser fusion power reactor SIRIUS-P
Fusion engineering and design, 1995-03, Vol.28 (1-2), p.665-672
1995
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Nuclear Analysis of the FIRE Ignition Device
FUSION TECHNOL, 2001-03, Vol.39 (2P2), p.393-397
2001
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Linked Neutronics and Hydrodynamics Calculations for the Z Pinch Driven Target of X-1
FUSION TECHNOL, 2001-03, Vol.39 (2P2), p.834-838
2001
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Assessment of Personnel Accessibility in the X-1 Facility
FUSION TECHNOL, 2001-03, Vol.39 (2P2), p.1003-1007
2001
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