ANS / Publications / Journals / Nuclear Science and Engineering

Fundamental Theory of the Direct Integration Method for Solving the Steady-State Integral Transport Equation for Radiation Shielding Calculation

Kiyoshi Takeuchi, Nobuo Sasamoto

Nuclear Science and Engineering / Volume 80 / Number 4 / April 1982 / Pages 536-553

Technical Paper / dx.doi.org/10.13182/NSE82-A18968

Direct Integration Method for Solving the Neutron Transport Equation in Three-Dimensional Geometry

Nobuo Sasamoto, Kiyoshi Takeuchi

Nuclear Science and Engineering / Volume 80 / Number 4 / April 1982 / Pages 554-569

Technical Paper / dx.doi.org/10.13182/NSE82-A18969

Accurate Evaluation of Multigroup Transfer Cross Sections and Their Legendre Coefficients

Kou-John Hong, J. Kenneth Shultis

Nuclear Science and Engineering / Volume 80 / Number 4 / April 1982 / Pages 570-578

Technical Paper / dx.doi.org/10.13182/NSE82-A18970

Multigroup Transfer Matrices for Charged-Particle and Neutron-Induced Reactions. Part II: An Analytic Integration of the Inner Integral

S. T. Perkins, P. C. Giles

Nuclear Science and Engineering / Volume 80 / Number 4 / April 1982 / Pages 579-585

Technical Paper / dx.doi.org/10.13182/NSE82-A18971

Calculated Neutron and Gamma-Ray Energy Spectra from 14-MeV Neutrons Streaming Through an Iron Duct: Comparison with Experiment

R. T. Santoro, R. G. Alsmiller, Jr., J. M. Barnes, G. T. Chapman, J. S. Tang

Nuclear Science and Engineering / Volume 80 / Number 4 / April 1982 / Pages 586-602

Technical Paper / dx.doi.org/10.13182/NSE82-A18972

A Measurement of the Average Number of Prompt Neutrons from Spontaneous Fission of Californium-252

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

Nuclear Science and Engineering / Volume 80 / Number 4 / April 1982 / Pages 603-629

Technical Paper / dx.doi.org/10.13182/NSE82-A18973

Fast Neutron Capture Cross Sections and Related Gamma-Ray Spectra of Niobium-93, Rhodium-103, and Tantalum-181

G. Reffo, F. Fabbri, K. Wisshak, F. Käppeler

Nuclear Science and Engineering / Volume 80 / Number 4 / April 1982 / Pages 630-647

Technical Paper / dx.doi.org/10.13182/NSE82-A18974

Multiregion Neutronics Model Based on Coarse Mesh Nodal Coupling Method for Transient Analyses of Boiling Water Reactors

Hiroshi Motoda, Tamotsu Hayase, Yasunori Bessho, Kanji Kato

Nuclear Science and Engineering / Volume 80 / Number 4 / April 1982 / Pages 648-666

Technical Paper / dx.doi.org/10.13182/NSE82-A18975

Experimental Determination of Sodium Evaporation Rates

W. Schütz, H. Sauter

Nuclear Science and Engineering / Volume 80 / Number 4 / April 1982 / Pages 667-672

Technical Paper / dx.doi.org/10.13182/NSE82-A18976

Sodium Boiling Pattern in Porous Blockages

D. Droste, H. M. Kottowski

Nuclear Science and Engineering / Volume 80 / Number 4 / April 1982 / Pages 673-688

Technical Paper / dx.doi.org/10.13182/NSE82-A18977

Radiation-Enhanced Saline Leaching of Silicate Glasses

William Primak

Nuclear Science and Engineering / Volume 80 / Number 4 / April 1982 / Pages 689-699

Technical Paper / dx.doi.org/10.13182/NSE82-A18978

Comparative Analysis of Integrated and Nonintegrated Fusion and Fission Energy Systems

K. F. Schoepf, M. Heindler, A. A. Harms

Nuclear Science and Engineering / Volume 80 / Number 4 / April 1982 / Pages 700-710

Technical Note / dx.doi.org/10.13182/NSE82-A18979

Spatial Convergence Properties of the Diamond Difference Method in x,y Geometry

Edward W. Larsen

Nuclear Science and Engineering / Volume 80 / Number 4 / April 1982 / Pages 710-713

Technical Note / dx.doi.org/10.13182/NSE82-A18980

Numerical Development and Investigation of the Factorized Kernel Approach for Solving Multidimensional Neutron Transport Problems

W. A. Wassef

Nuclear Science and Engineering / Volume 80 / Number 4 / April 1982 / Pages 714-720

Technical Note / dx.doi.org/10.13182/NSE82-A18981

A Self-Powered Neutron Detector with a Fissile Emitter

Helmuth Boeck

Nuclear Science and Engineering / Volume 80 / Number 4 / April 1982 / Pages 720-723

Technical Note / dx.doi.org/10.13182/NSE82-A18982