Nuclear Science and Engineering


ISSN: 0029-5639        年代:1978
当前卷期:Volume 67  issue 2     [ 查看所有卷期 ]

年代:1978
 
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1. Spectrum of the Multigroup-Multipoint Diffusion Operator with Delayed Neutrons
  Nuclear Science and Engineering,   Volume  67,   Issue  2,   1978,   Page  147-161

DevooghtJ.,  

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2. The Application of the Symmetric SOR and the Symmetric SIP Methods for the Numerical Solution of the Neutron Diffusion Equation
  Nuclear Science and Engineering,   Volume  67,   Issue  2,   1978,   Page  162-171

WangH. H.,  

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3. Spatial Distribution Measurements of Fission Neutrons in Water as an Oxygen Data Test
  Nuclear Science and Engineering,   Volume  67,   Issue  2,   1978,   Page  172-183

GreenL.,   UlloJ. J.,  

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4. A Measurement of the Total Neutron Cross Section of Iron-58 in the Energy Range from 7 to 325 keV
  Nuclear Science and Engineering,   Volume  67,   Issue  2,   1978,   Page  184-189

BeerH.,   HongLy Di,   KäppelerF.,  

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5. Unified Absolute Differential Cross Sections for Neutron Production by the Hydrogen Isotopes for Charged-Particle Energies Between 6 and 17 MeV
  Nuclear Science and Engineering,   Volume  67,   Issue  2,   1978,   Page  190-220

DrosgM.,  

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6. Improved Resonance Formulas for Cross Sections of Fissile Elements
  Nuclear Science and Engineering,   Volume  67,   Issue  2,   1978,   Page  221-234

SegevM.,  

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7. A Computational Study of the Density and Temperature Distribution in a Freely Expanding Uranium Hexafluoride Gas
  Nuclear Science and Engineering,   Volume  67,   Issue  2,   1978,   Page  235-246

MikamiH.,  

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8. A Calculation Model for Predicting Concentrations of Radioactive Corrosion Products in the Primary Coolant of Boiling Water Reactors
  Nuclear Science and Engineering,   Volume  67,   Issue  2,   1978,   Page  247-254

UchidaShunsuke,   KikuchiMakoto,   AsakuraYamato,   YusaHideo,   OhsumiKatsumi,  

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9. Fusion-Fission Analogy andTnτCriterion for Fusion Plasmas
  Nuclear Science and Engineering,   Volume  67,   Issue  2,   1978,   Page  255-257

McNallyJ. Rand,  

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10. Benchmark Calculations for a Sodium-Cooled Breeder Reactor by Two- and Three-Dimensional Diffusion Methods—II
  Nuclear Science and Engineering,   Volume  67,   Issue  2,   1978,   Page  257-259

BuckelG.,   KüfnerK.,   StehleB.,  

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