ANS / Publications / Journals / Nuclear Science and Engineering

Photon Transport Studies in Media with Strongly Anisotropic Scattering with the Boltzmann-Fokker-Planck Equation

Anil Kumar, Jacques Ligou

Nuclear Science and Engineering / Volume 96 / Number 1 / May 1987 / Pages 1-7

Technical Paper / dx.doi.org/10.13182/NSE87-A16358

Fission Product Yields for Fast-Neutron Fission of 243,244,246,248_Cm

J. K. Dickens

Nuclear Science and Engineering / Volume 96 / Number 1 / May 1987 / Pages 8-16

Technical Paper / dx.doi.org/10.13182/NSE87-A16359

Gadolinium Burnable Absorber Optimization by the Method of Conjugate Gradients

Clifton R. Drumm, John C. Lee

Nuclear Science and Engineering / Volume 96 / Number 1 / May 1987 / Pages 17-29

Technical Paper / dx.doi.org/10.13182/NSE87-1

Optimum Arrangement for the Neutron Dose Rate of an Iron-Polyethylene Shielding System

Kohtaro Ueki, Yoshihito Namito

Nuclear Science and Engineering / Volume 96 / Number 1 / May 1987 / Pages 30-38

Technical Paper / dx.doi.org/10.13182/NSE87-A16361

Cross Sections for Two-Body Sequential Decay Reactions

M. D. Baker, H. D. Knox, E. Breitenberger

Nuclear Science and Engineering / Volume 96 / Number 1 / May 1987 / Pages 39-45

Technical Note / dx.doi.org/10.13182/NSE87-A16362

Stability of Muon Catalyzed Fusion Systems

D. R. Wyman, R. E. Stone, A. A. Harms

Nuclear Science and Engineering / Volume 96 / Number 1 / May 1987 / Pages 46-51

Technical Note / dx.doi.org/10.13182/NSE87-A16363

⁷Li(n,n’t)⁴He Reaction Cross Section via Tritium Counting

S. M. Qaim, R. Wölfle

Nuclear Science and Engineering / Volume 96 / Number 1 / May 1987 / Pages 52-57

Technical Note / dx.doi.org/10.13182/NSE87-A16364

R-Matrix Analysis of the ²⁴¹ Pu Cross Sections up to 100 eV

H. Derrien, N. M. Larson, G. de Saussure, R. B. Perez

Nuclear Science and Engineering / Volume 96 / Number 1 / May 1987 / Pages 58-65

Technical Note / dx.doi.org/10.13182/NSE87-A16365

Investigations of Electromagnetic Cascades Produced in Lead by 2.5-GeV Bremsstrahlung

Hideo Hirayama, Syuichi Ban, Shigeyuki Miura

Nuclear Science and Engineering / Volume 96 / Number 1 / May 1987 / Pages 66-72

Technical Note / dx.doi.org/10.13182/NSE87-A16366

Improvement of Passive Safety of Reactors

Yoshiro Asahi, Tadashi Watanabe,Hiroaki Wakabayashi

Nuclear Science and Engineering / Volume 96 / Number 1 / May 1987 / Pages 73-84

Technical Note / dx.doi.org/10.13182/NSE87-A16367

Optimization of Core Reload Design for Low-Leakage Fuel Management in Pressurized Water Reactors

Young Jin Kim,* Thomas J. Downar, Alexander Sesonske

Nuclear Science and Engineering / Volume 96 / Number 2 / June 1987 / Pages 85-101

Technical Paper / dx.doi.org/10.13182/NSE87-A16369

Fission Rates and High-Energy Neutron Fluxes in the Purdue Fast Breeder Blanket Facility

Helio C. Vital,* F. M. Clikeman, K. O. Ott

Nuclear Science and Engineering / Volume 96 / Number 2 / June 1987 / Pages 102-111

Technical Paper / dx.doi.org/10.13182/NSE87-A16370

Resonance Self-Shielding near Zone Interfaces

S. C. Mo, K. O. Ott

Nuclear Science and Engineering / Volume 96 / Number 2 / June 1987 / Pages 112-121

Technical Paper / dx.doi.org/10.13182/NSE87-A16371

Nuclear Data for ²³⁵U, ²³⁸U, and ²³⁹Pu in the Unresolved Resonance Region

A. A. Vankov and V. F. Ukraintsev, N. Yaneva, S. Toshkov, A. Mateeva

Nuclear Science and Engineering / Volume 96 / Number 2 / June 1987 / Pages 122-136

Technical Paper / dx.doi.org/10.13182/NSE87-A16372

Thermocapillary-Induced Breakup of Molten Cladding Films

P. R. Henkel

Nuclear Science and Engineering / Volume 96 / Number 2 / June 1987 / Pages 137-144

Technical Paper / dx.doi.org/10.13182/NSE87-A16373

Estimation of Failed Sensor Outputs

J. Louis Tylee

Nuclear Science and Engineering / Volume 96 / Number 2 / June 1987 / Pages 145-152

Technical Paper / dx.doi.org/10.13182/NSE87-A16374

Some Aspects of the Forward Method for High-Order Sensitivity Analysis

Yigal Ronen

Nuclear Science and Engineering / Volume 96 / Number 2 / June 1987 / Pages 153-158

Technical Paper / dx.doi.org/10.13182/NSE87-A16375

Measurement and Status of Neutron Scattering on ¹Li and ⁷Li Between 6 and 14 MeV

D. Schmidt, D. Seeliger, G. N. Lovchikova, A. M. Trufanov

Nuclear Science and Engineering / Volume 96 / Number 2 / June 1987 / Pages 159-167

Technical Note / dx.doi.org/10.13182/NSE87-A16376

Time Behavior of the Neutron Flux at the Vessel Boundary of a Boiling Water Reactor Power Plant

A. Cesana, M. Terrani, G. Sandrelli

Nuclear Science and Engineering / Volume 96 / Number 2 / June 1987 / Pages 168-170

Technical Note / dx.doi.org/10.13182/NSE87-A16377

GERES: A Code to Process MC2-II Data for Heterogeneous Fast Reactor Cell Calculation

M. Galli

Nuclear Science and Engineering / Volume 96 / Number 2 / June 1987 / Pages 171-172

Computer Code Abstract / dx.doi.org/10.13182/NSE87-A16378

A Critique of Three Methodologies for Estimating the Probability of Containment Failure Due to Steam Explosions

Marshall Berman

Nuclear Science and Engineering / Volume 96 / Number 3 / July 1987 / Pages 173-191

Technical Paper / dx.doi.org/10.13182/NSE87-A16380

A Rigorous Pole Representation of Multilevel Cross Sections and Its Practical Applications

R. N. Hwang

Nuclear Science and Engineering / Volume 96 / Number 3 / July 1987 / Pages 192-209

Technical Paper / dx.doi.org/10.13182/NSE87-A16381

Calculation of Capture Cross Sections and Gamma-Ray Spectra Following the Interaction of Neutrons with ¹⁸¹Ta and ¹⁹⁷Au

Nobuhiro Yamamuro, Kazuyuki Udagawa, Toshihiro Natsume

Nuclear Science and Engineering / Volume 96 / Number 3 / July 1987 / Pages 210-220

Technical Paper / dx.doi.org/10.13182/NSE87-A16382

On the Generalized Neutron Noise Formulation with Application to a Coupled Core Reactor

Shyn-Jen Lee

Nuclear Science and Engineering / Volume 96 / Number 3 / July 1987 / Pages 221-233

Technical Paper / dx.doi.org/10.13182/NSE87-A16383

Neutron Transport Theory in a Ring Reactor

M. M. R. Williams

Nuclear Science and Engineering / Volume 96 / Number 3 / July 1987 / Pages 234-240

Technical Note / dx.doi.org/10.13182/NSE87-A16384

A Comparison of Gamma-Ray Buildup Factors for Low-Z Material and for Low Energies Using Discrete Ordinates and Point Monte Carlo Methods

Yoshiko Harima, Hideo Hirayama, Toshio Ishikawa, Yukio Sakamoto, Shun-ich Tanaka

Nuclear Science and Engineering / Volume 96 / Number 3 / July 1987 / Pages 241-252

Technical Note / dx.doi.org/10.13182/NSE87-A16385

Effect of a Mixing Vane in a Three-Subchannel Simulated Fuel Rod Bundle Using a Gamma Camera

Alireza Sedaghat, Robert Macduff, Frank Castellana

Nuclear Science and Engineering / Volume 96 / Number 3 / July 1987 / Pages 253-259

Technical Note / dx.doi.org/10.13182/NSE87-A16386

LEPRICON Analysis of Pressure Vessel Surveillance Dosimetry Inserted into H. B. Robinson-2 During Cycle 9

R. E. Maerker

Nuclear Science and Engineering / Volume 96 / Number 4 / August 1987 / Pages 263-289

Technical Paper / dx.doi.org/10.13182/NSE87-A16391

DOXCY—A Discrete Ordinates Approximation of Neutron Transport in Heterogeneous Rod Lattices

H. Dietmar Märtens, D. Stegemann

Nuclear Science and Engineering / Volume 96 / Number 4 / August 1987 / Pages 290-302

Technical Paper / dx.doi.org/10.13182/NSE87-A16392

Prompt Response Self-Powered Neutron Detectors I: The Effective Charge per Neutron Captured

Maria Do Carmo Lopes, Jorge Molina Avila

Nuclear Science and Engineering / Volume 96 / Number 4 / August 1987 / Pages 303-309

Technical Paper / dx.doi.org/10.13182/NSE87-A16393

Prompt Response Self-Powered Neutron Detectors II: Thermal and Epithermal Sensitivities

Jorge Molina Avila, Maria Do Carmo Lopes

Nuclear Science and Engineering / Volume 96 / Number 4 / August 1987 / Pages 310-317

Technical Paper / dx.doi.org/10.13182/NSE87-A16394

Parameters of the 1.056-eV Resonance in ²⁴⁰Pu and the 2200 m/s Neutron Total Cross Sections of ²³⁵U, ²³⁹Pu, and ²⁴⁰Pu

R. Spencer, J. A. Harvey, N. W. Hill, L. W. Weston

Nuclear Science and Engineering / Volume 96 / Number 4 / August 1987 / Pages 318-329

Technical Paper / dx.doi.org/10.13182/NSE87-A16395

Effect of Fluorescence in Deep Penetration of Gamma Rays

K. V. Subbaiah, A. Natarajan

Nuclear Science and Engineering / Volume 96 / Number 4 / August 1987 / Pages 330-342

Technical Paper / dx.doi.org/10.13182/NSE87-A16396