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E 1.99:ornl/csd/tm-224
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Assessment of computational performance in nuclear criticality |
1 |
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E 1.99:ornl/csd/tm-225
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Review of PGDP assessment of criticality safety problems in increasing product assay to 5 wt % ²³⁵U |
1 |
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E 1.99:ornl/csd/tm-227
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Parametric study of radiation dose rates from rail and truck spent fuel transport casks |
1 |
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E 1.99:ornl/csd/tm-228
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Particle size distributions formed by atmospheric hydrolysis of uranium hexafluoride |
1 |
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E 1.99:ornl/csd/tm-237
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Scoping study of casks shipped from the MRS facility to various repository sites |
1 |
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E 1.99:ornl/csd/tm-238
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Validation of KENO V.a Comparison with Critical Experiments |
1 |
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E 1.99:ornl/csd/tm-239
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HEATING6 analysis of international thermal benchmark problem sets 1 and 2 |
1 |
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E 1.99:ornl/csd/tm-240
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Upgrade of the GRESS (test version D) precompiler to allow triply-dimensioned arrays |
1 |
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E 1.99:ornl/csd/tm-244
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Reactivity and isotopic composition of spent PWR (pressurized-water-reactor) fuel as a function of initial enrichment, burnup, and cooling time |
1 |
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E 1.99:ornl/csd/tm-246
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Assessment of shielding analysis methods, codes, and data for spent fuel transport/storage applications. [Radiation dose rates from shielded spent fuels and high-level radioactive waste] |
1 |
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E 1.99:ornl/csd/tm-248
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CAPSIZE A personal computer program and cross-section library for determining the shielding requirements, size, and capacity of shipping casks subject to various proposed objectives. |
1 |
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E 1.99:ornl/csd/tm-251
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Multicode comparison of selected source-term computer codes |
1 |
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E 1.99:ornl/csd/tm-259
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Comparison of radiation spectra from selected source-term computer codes |
1 |
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E 1.99:ornl/csd/tm-266
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Actinide nuclear data for reactor physics calculations |
1 |
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E 1.99:ornl/csd/tm-268
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Feasibility assessment of burnup credit in the criticality analysis of shipping casks with boiling water reactor spent fuel |
1 |
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E 1.99:ornl/csd/tm-269
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Scheduling Algorithm for Improving Lift (SAIL) Documentation for initial operating capability. |
1 |
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E 1.99:ornl/csd/tm--272
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Benchmark shielding calculations for the NEACRP [Nuclear Energy Agency-Committee on Reactor Physics] Working Group on shielding assessment of transportation packages |
1 |
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E 1.99:ornl/csd/tm--281
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An introduction to computer viruses |
1 |
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E 1.99:ornl/csd/tm-281
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An introduction to computer viruses |
1 |
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E 1.99:ornl/csd/tm--283
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AMPX-77 A modular code system for generating coupled multigroup neutron-gamma cross-section libraries from ENDF/B-IV and/or ENDF/B-V. |
1 |
