ANS / Publications / Journals / Nuclear Science and Engineering

Reaction Cross Sections on Carbon for Neutron Energies from 11.5 to 19 MeV

B. Antolković, G. Dietze, H. Klein

Nuclear Science and Engineering / Volume 107 / Number 1 / January 1991 / Pages 1-21

Technical Paper / dx.doi.org/10.13182/NSE91-A23777

Determination of Neutron-Induced Alpha-Particle Cross Sections on Carbon Using the Response of a Liquid Scintillation Detector

H. J. Brede, G. Dietze, H. Klein, H. Schölermann

Nuclear Science and Engineering / Volume 107 / Number 1 / January 1991 / Pages 22-34

Technical Paper / dx.doi.org/10.13182/NSE91-A23778

²⁵²Cf-Source-Driven Noise Measurements of Subcriticality for a Slab Tank of Aqueous Pu-U Nitrate

J. T. Mihalczo, E. D. Blakeman, G. E. Ragan, R. C. Kryter, H. Seino, R. C. Robinson

Nuclear Science and Engineering / Volume 107 / Number 1 / January 1991 / Pages 35-57

Technical Paper / dx.doi.org/10.13182/NSE91-A23779

Comparison of Vectorization Methods Used in a Monte Carlo Code

Masayuki Nakagawa, Takamasa Mori, Makoto Sasaki

Nuclear Science and Engineering / Volume 107 / Number 1 / January 1991 / Pages 58-66

Technical Paper / dx.doi.org/10.13182/NSE91-A23780

Study of Slab Transmission and Reflection

C. M. Eisenhauer

Nuclear Science and Engineering / Volume 107 / Number 1 / January 1991 / Pages 67-81

Technical Paper / dx.doi.org/10.13182/NSE91-A23781

Physics of the Conceptual Design of Intense Steady Neutron Sources

Felix C. Difilippo

Nuclear Science and Engineering / Volume 107 / Number 1 / January 1991 / Pages 82-98

Technical Note / dx.doi.org/10.13182/NSE91-A23782

Preparation, Conduct, and Experimental Results of the AVR Loss-of-Coolant Accident Simulation Test

K. Krüger, A. Bergerfurth, S. Burger, P. Pohl, M. Wimmers, J. C. Cleveland

Nuclear Science and Engineering / Volume 107 / Number 2 / February 1991 / Pages 99-113

Technical Paper / dx.doi.org/10.13182/NSE91-A15725

Monte Carlo Calculation of Delayed Gamma Dose Rate in Complex Geometry Using the Concept of Effective Delayed Gamma Production Cross Section

S. L. Liew, L. P. Ku

Nuclear Science and Engineering / Volume 107 / Number 2 / February 1991 / Pages 114-130

Technical Paper / dx.doi.org/10.13182/NSE91-A15726

Use of Qualitative and Quantitative Models in the Supervision of Power Plant Operations

Alex Galperin, Jean-Michel Evrard

Nuclear Science and Engineering / Volume 107 / Number 2 / February 1991 / Pages 131-141

Technical Paper / dx.doi.org/10.13182/NSE91-A15727

KNOWBOT: An Adaptive Data Base Interface

A. Sharif Heger, Billy V. Koen

Nuclear Science and Engineering / Volume 107 / Number 2 / February 1991 / Pages 142-157

Technical Paper / dx.doi.org/10.13182/NSE91-A15728

Adaptive Predictive Control of a Boiling Water Reactor

Chaung Lin, Shyurng-Rern Chang

Nuclear Science and Engineering / Volume 107 / Number 2 / February 1991 / Pages 158-172

Technical Paper / dx.doi.org/10.13182/NSE91-A15729

A Mechanism for Out-of-Phase Power Instabilities in Boiling Water Reactors

José March-Leuba, E. D. Blakeman

Nuclear Science and Engineering / Volume 107 / Number 2 / February 1991 / Pages 173-179

Technical Note / dx.doi.org/10.13182/NSE91-A15730

Monte Carlo Analysis of a Neutron Streaming Experiment

S. N. Cramer, T. Y. Lee

Nuclear Science and Engineering / Volume 107 / Number 2 / February 1991 / Pages 180-187

Technical Note / dx.doi.org/10.13182/NSE91-A15731

A Model for Neutron Scattering Off Heavy Isotopes That Accounts for Thermal Agitation Effects

Mohamed Ouisloumen, Richard Sanchez

Nuclear Science and Engineering / Volume 107 / Number 3 / March 1991 / Pages 189-200

Technical Paper / dx.doi.org/10.13182/NSE89-186

An Integral S_n Method for Large-Memory Supercomputers

S. P. Monahan, W. L. Filippone

Nuclear Science and Engineering / Volume 107 / Number 3 / March 1991 / Pages 201-216

Technical Paper / dx.doi.org/10.13182/NSE91-A23785

Synthetic Acceleration Methods for Linear Transport Problems with Highly Anisotropic Scattering

Kassem M. Khattab, Edward W. Larsen

Nuclear Science and Engineering / Volume 107 / Number 3 / March 1991 / Pages 217-227

Technical Paper / dx.doi.org/10.13182/NSE91-A23786

The Integral Line-Beam Method for Gamma Skyshine Analysis

J. Kenneth Shultis, R. E. Faw, M. S. Bassett

Nuclear Science and Engineering / Volume 107 / Number 3 / March 1991 / Pages 228-245

Technical Paper / dx.doi.org/10.13182/NSE91-A23787

Space-Dependent Core/Reflector Boundary Conditions Generated by the Boundary Element Method for Pressurized Water Reactors

Masafumi Itagaki, Carlos A. Brebbia

Nuclear Science and Engineering / Volume 107 / Number 3 / March 1991 / Pages 246-264

Technical Paper / dx.doi.org/10.13182/NSE91-A23788

Benchmark Calculations for the Doppler Coefficient of Reactivity

Russell D. Mosteller, Laurence D. Eisenhart, Robert C. Little, Walter J. Eich, Jason Chao

Nuclear Science and Engineering / Volume 107 / Number 3 / March 1991 / Pages 265-271

Technical Paper / dx.doi.org/10.13182/NSE91-A23789

The Weighting Function of a Neutron Capture Detection System

F. Corvi, G. Fioni, F. Gasperini, P. B. Smith

Nuclear Science and Engineering / Volume 107 / Number 3 / March 1991 / Pages 272-283

Technical Paper / dx.doi.org/10.13182/NSE91-A23790

Dynamic Character of Failure State in Damage Accumulation Processes

Dov Ingman, Leib Reznik

Nuclear Science and Engineering / Volume 107 / Number 3 / March 1991 / Pages 284-290

Technical Paper / dx.doi.org/10.13182/NSE91-A23791

Reactor Diagnostics Rule Generation Through Statistical Pattern Recognition

Jaques Reifman, John C. Lee

Nuclear Science and Engineering / Volume 107 / Number 4 / April 1991 / Pages 291-314

Technical Paper / dx.doi.org/10.13182/NSE91-A23793

Transport and Release of Radioactive Fission Products in Nuclear Fuels: The New Analytical Method of the MITRA Code

M. Gardani, C. Ronchi

Nuclear Science and Engineering / Volume 107 / Number 4 / April 1991 / Pages 315-329

Technical Paper / dx.doi.org/10.13182/NSE91-A23794

An Angular Multigrid Acceleration Technique for S_n Equations with Highly Forward-Peaked Scattering

J. E. Morel, T. A. Manteuffel

Nuclear Science and Engineering / Volume 107 / Number 4 / April 1991 / Pages 330-342

Technical Paper / dx.doi.org/10.13182/NSE91-A23795

One-Speed Neutron Transport Eigenvalues for Reflected Slabs and Spheres

Ninos S. Garis

Nuclear Science and Engineering / Volume 107 / Number 4 / April 1991 / Pages 343-358

Technical Paper / dx.doi.org/10.13182/NSE91-A23796

Optimization of Linear Monte Carlo Calculations

Eugene S. Troubetzkoy

Nuclear Science and Engineering / Volume 107 / Number 4 / April 1991 / Pages 359-364

Technical Paper / dx.doi.org/10.13182/NSE91-A23797

Cross Sections and Spectra for the ⁵⁴Fe and ⁵⁶Fe (n,xp) and (n,xα) Reactions Between 8 and 15 MeV

S. K. Saraf, C. E. Brient, P. M. Egun, S. M. Grimes, V. Mishra, R. S. Pedroni

Nuclear Science and Engineering / Volume 107 / Number 4 / April 1991 / Pages 365-373

Technical Paper / dx.doi.org/10.13182/NSE88-120

Self-Powered Detector Response to Thermal and Epithermal Neutron Flux

M. N. Agu, H. Petitcolas

Nuclear Science and Engineering / Volume 107 / Number 4 / April 1991 / Pages 374-384

Technical Paper / dx.doi.org/10.13182/NSE91-A23799

Gamma-Ray Attenuation in the Vicinity of the K Edge in Molybdenum, Tin, Lanthanum, Gadolinium, Tungsten, Lead, and Uranium

Yoshiko Harima, D. K. Trubey, Y. Sakamoto, S. Tanaka

Nuclear Science and Engineering / Volume 107 / Number 4 / April 1991 / Pages 385-393

Technical Paper / dx.doi.org/10.13182/NSE91-A23800

A Problem in the Teaching of Reactor Kinetics

Lawrence Ruby

Nuclear Science and Engineering / Volume 107 / Number 4 / April 1991 / Pages 394-396

Technical Note / dx.doi.org/10.13182/NSE91-A23801