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Home / Publications / Journals / Nuclear Science and Engineering / Volume 94 / Number 4

Volume 94

Number 4

Accounting for Changing Source Distributions in Light Water Reactor Surveillance Dosimetry Analysis

R. E. Maerker, M. L. Williams, B. L. Broadhead

Nuclear Science and Engineering / Volume 94 / Number 4 / December 1986 / Pages 291-308

Technical Paper / dx.doi.org/10.13182/NSE86-A18342

A Linear Discontinuous Finite Difference Formulation for Synthetic Coarse-Mesh Few-Group Diffusion Calculations

José M. Aragonés, Carol Ahnert

Nuclear Science and Engineering / Volume 94 / Number 4 / December 1986 / Pages 309-322

Technical Paper / dx.doi.org/10.13182/NSE86-A18343

Variance Reduction Under Exponential and Scattering Angle Biasing: An Analytic Approach

R. Indira, T. M. John

Nuclear Science and Engineering / Volume 94 / Number 4 / December 1986 / Pages 323-336

Technical Paper / dx.doi.org/10.13182/NSE86-A18344

Independent Fission Yield Measurements

Hans Otto Denschlag

Nuclear Science and Engineering / Volume 94 / Number 4 / December 1986 / Pages 337-352

Technical Paper / dx.doi.org/10.13182/NSE86-A18345

Composite Delayed Neutron Energy Spectra for Thermal Fission of 235U

R. S. Tanczyn, Q. Sharfuddin, W. A. Schier, D. J. Pullen, M. H. Haghighi, L. Fisteag, and G. P. Couchell

Nuclear Science and Engineering / Volume 94 / Number 4 / December 1986 / Pages 353-364

Technical Paper / dx.doi.org/10.13182/NSE86-A18346

Measurements of the Energy Dependence of Prompt Neutron Emission from 233U, 235U, and 239Pu for En = 0.0005 to 10 MeV Relative to Emission from Spontaneous Fission of 252Cf

R. Gwin, R. R. Spencer, R. W. Ingle

Nuclear Science and Engineering / Volume 94 / Number 4 / December 1986 / Pages 365-379

Technical Paper / dx.doi.org/10.13182/NSE86-A18347

Higher Order Perturbation Theory — An Example for Discussion

J. D. Lewins, G. Parks, A. L. Babb

Nuclear Science and Engineering / Volume 94 / Number 4 / December 1986 / Pages 380-392

Technical Paper / dx.doi.org/10.13182/NSE86-A18348

Calculation of the Neutron Flux in a Heterogeneous Reactor Polycell with Fuel Multirod Clusters in a One-Group P3 Approximation

V. E. Raevskaya

Nuclear Science and Engineering / Volume 94 / Number 4 / December 1986 / Pages 393-408

Technical Paper / dx.doi.org/10.13182/NSE86-A18349

Direct and Indirect Computation of the Transport Equation Eigenvalues

R. L. Perel, J.J. Wagschal

Nuclear Science and Engineering / Volume 94 / Number 4 / December 1986 / Pages 409-412

Technical Note / dx.doi.org/10.13182/NSE94-409

Mass Distribution in the Fission of 232Th by Degraded-Fission-Spectrum Neutrons

Albert E. Richardson, Harold L. Wright, John L. Meason, James R. Smith

Nuclear Science and Engineering / Volume 94 / Number 4 / December 1986 / Pages 413-425

Technical Note / dx.doi.org/10.13182/NSE86-A18351

 

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