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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 | doi.org/10.13182/NSE87-A16358
Fission Product Yields for Fast-Neutron Fission of 243,244,246,248Cm
J. K. Dickens
Nuclear Science and Engineering | Volume 96 | Number 1 | May 1987 | Pages 8-16
Technical Paper | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | doi.org/10.13182/NSE87-A16396
