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Publications by H. Menlove
Neutron Coincidence Counter for MOX Fuel Pins in Storage Trays: Users' Manual
Related publications
Development of MOX Fuel for Nuclear Power Plant.
Journal of the Fuel Society of Japan
Users Manual for the Optime System
Computer Physics Communications
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Design Study for MOX Fuel Rod Scanner for ATR Fuel Fabrication. Phase I: Design of Active Neutron Scanner. Phase II: Design of Passive Neutron Scanner. Phase III: Design of Passive Gamma-Ray Scanner
Thermally Induced Gallium Removal From Plutonium Dioxide for MOX Fuel Production
Journal of Nuclear Materials
High Energy Physics
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Application of Advanced Neutron Absorbing Materials to Structural Material of Inner Basket of Storage Casks for High Burnup and MOX Spent Fuels.
Journal of the Atomic Energy Society of Japan / Atomic Energy Society of Japan
Direction and Region Dependent Cross Sections for Use to MOX Fuel Analysis
Journal of Nuclear Science and Technology
High Energy Physics
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Neutron Generators for Spent Fuel Assay
PETSc Users Manual: Revision 3.11
PETSc Users Manual: Revision 3.10
