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Number 1
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Number 4

Number 1

A Study of Liquid Mass Transport in Annular Air-Water Flow
William D. Hinkle, Henri Fenech
Nuclear Science and Engineering | Volume 87 | Number 1 | May 1984 | Pages 2-12
Technical Paper | doi.org/10.13182/NSE84-A17440
Thermal Design Concepts for the Rotating Fluidized Bed Reactor
O. C. Jones, Jr.
Nuclear Science and Engineering | Volume 87 | Number 1 | May 1984 | Pages 13-27
Technical Paper | doi.org/10.13182/NSE84-A17441
Covariances of Neutron Fluxes and Cross Sections in Group Structure Variation
M. Marseguerra, V. Sangiust, M. Petilli
Nuclear Science and Engineering | Volume 87 | Number 1 | May 1984 | Pages 28-33
Technical Paper | doi.org/10.13182/NSE84-A17442
Preequilibrium Emission of Protons from ⁹³Nb(n,p) Reaction at 14 MeV
N. Koori, Y. Ohsawa, I. Kumabe
Nuclear Science and Engineering | Volume 87 | Number 1 | May 1984 | Pages 34-40
Technical Paper | doi.org/10.13182/NSE84-A17443
The ¹²C(n,α) Reaction and the Kerma Factor for Carbon at E_n = 14.1 MeV
R. C. Haight, S. M. Grimes, R. G. Johnson, H. H. Barschal
Nuclear Science and Engineering | Volume 87 | Number 1 | May 1984 | Pages 41-47
Technical Paper | doi.org/10.13182/NSE84-A17444
Neutron Capture in s-Wave Resonances of Nickel-64
K. Wisshak, F. Käppeler, R. L. Macklin, G. Reffo, F. Fabbri
Nuclear Science and Engineering | Volume 87 | Number 1 | May 1984 | Pages 48-58
Technical Paper | doi.org/10.13182/NSE84-A17445
Track Length Estimation Applied to Point Detectors
H. Rief, A. Dubi, T. Elperin
Nuclear Science and Engineering | Volume 87 | Number 1 | May 1984 | Pages 59-71
Technical Paper | doi.org/10.13182/NSE84-A17446
Diffusion Coefficients for Fast Reactor Hexagonal Assemblies
Pierre Benoist, Tomasz Duracz
Nuclear Science and Engineering | Volume 87 | Number 1 | May 1984 | Pages 72-80
Technical Note | doi.org/10.13182/NSE84-A17447
Sensitivity Coefficients for Leakage and Nonleakage Components of Sodium Void Worth
T. Takeda, T. Yamamoto
Nuclear Science and Engineering | Volume 87 | Number 1 | May 1984 | Pages 80-84
Technical Note | doi.org/10.13182/NSE84-A17448
Extrapolation Distance in the Cylindrical Milne Problem in One- and Two-Group Transport Theory
Tomasz Błeński
Nuclear Science and Engineering | Volume 87 | Number 1 | May 1984 | Pages 84-96
Technical Note | doi.org/10.13182/NSE84-A17449
Alternate Methods of Utilizing Cross-Section Sensitivity Coefficients in Radiation Shielding Problems
S. I. Bhuiyan, R. W. Roussin, J. L. Lucius, J. H. Marable, D. E. Bartine
Nuclear Science and Engineering | Volume 87 | Number 1 | May 1984 | Pages 96-102
Technical Note | doi.org/10.13182/NSE84-A17450

Number 2

Table of Contents
Terminology for Adjoint Equations and Operators (Jeffery Lewins)
BALTORO: A General Purpose Code for Coupling of Monte Carlo and Discrete Ordinates Radiation Transport Calculations (Jan M. Zazula)

Neutron Transport Calculations in Cylindrical Geometry
C. E. Siewert, J. R. Thomas, Jr.
Nuclear Science and Engineering | Volume 87 | Number 2 | June 1984 | Pages 107-112
Technical Paper | doi.org/10.13182/NSE84-A17705
Monte Carlo Calculation and Analytical Approximation of Gamma-Ray Buildup Factors in Air
P. Jacob, H. G. Paretzke, J. Wölfel
Nuclear Science and Engineering | Volume 87 | Number 2 | June 1984 | Pages 113-122
Technical Paper | doi.org/10.13182/NSE84-A17706
Evaluation of Neutron Skyshine from a Cyclotron
Katsumi Hayashi, Takashi Nakamura
Nuclear Science and Engineering | Volume 87 | Number 2 | June 1984 | Pages 123-135
Technical Paper | doi.org/10.13182/NSE84-A17707
Estimation of Population Variance in Contributon Monte Carlo
P. K. Sarkar, M. A. Prasad
Nuclear Science and Engineering | Volume 87 | Number 2 | June 1984 | Pages 136-151
Technical Paper | doi.org/10.13182/NSE84-A17708
Concept of Shielding Characteristics for Spent Fuel Shipping Casks
Hisao Yamakoshi
Nuclear Science and Engineering | Volume 87 | Number 2 | June 1984 | Pages 152-180
Technical Paper | doi.org/10.13182/NSE84-A17709
Distribution of Delayed Neutron Yields Versus Proton, Neutron, and Mass Numbers: Application to Proton Pairing in Fission Yields
P. L. Reeder, R. A. Warner
Nuclear Science and Engineering | Volume 87 | Number 2 | June 1984 | Pages 181-189
Technical Note | doi.org/10.13182/NSE84-A17710
A Deuteron Energy Loss Evaluation in a Solid Ti-T Target Used for the T(d,n)⁴He Reaction
A. Tsechanski, G. Shani
Nuclear Science and Engineering | Volume 87 | Number 2 | June 1984 | Pages 189-194
Technical Note | doi.org/10.13182/NSE84-A17711

Number 3

Table of Contents
Foreword (Karl Wirtz)
Preface: Fast Critical Facilities—Present Status and Future Potential (F. Helm)

Experimental Studies of Radially Heterogeneous Liquid-Metal Fast Breeder Reactor Critical Assemblies at the Zero-Power Plutonium Reactor
H. F. McFarlane, S. G. Carpenter, P. J. Collins, D. N. Olsen, S. B. Brumbach
Nuclear Science and Engineering | Volume 87 | Number 3 | July 1984 | Pages 204-232
Technical Paper | doi.org/10.13182/NSE84-A17779
Parametric Studies on Heterogeneous Cores for Fast Breeder Reactors: The Pre-Racine and Racine Experimental Programs
G. Humbert, F. Kappler, M. Martini, G. Norvez, G. Rimpault, B. Ruelle, A. Stanculescu, W. Scholtyssek
Nuclear Science and Engineering | Volume 87 | Number 3 | July 1984 | Pages 233-251
Technical Paper | doi.org/10.13182/NSE84-A17780
Critical Experiments Using an Axially Heterogeneous Assembly and Their Analysis
J. Hirota, M. Nakano, S. Iijima, K. Shirakata
Nuclear Science and Engineering | Volume 87 | Number 3 | July 1984 | Pages 252-261
Technical Paper | doi.org/10.13182/NSE84-A17781
Worths and Interactions of Simulated Fast Breeder Reactor Control Rods in ZEBRA and SNEAK Assemblies
H. Giese, S. Pilate, J. M. Stevenson
Nuclear Science and Engineering | Volume 87 | Number 3 | July 1984 | Pages 262-282
Technical Paper | doi.org/10.13182/NSE84-A17782
An Experimental Study of Reactivity Changes and Flux Distortion in Simulated LMFBR Meltdown Cores
M. Nakano, H. Tsunoda, J. Hirota
Nuclear Science and Engineering | Volume 87 | Number 3 | July 1984 | Pages 283-294
Technical Paper | doi.org/10.13182/NSE84-A17783
Measurements and Computation of the Reactivity Effects of Accident-Caused Core Distortions in Liquid-Metal Fast Breeder Reactors
F. Helm, G. Henneges, W. Maschek
Nuclear Science and Engineering | Volume 87 | Number 3 | July 1984 | Pages 295-313
Technical Paper | doi.org/10.13182/NSE84-A17784
Recent Developments in the Small-Sample Reactivity Discrepancy
K. S. Smith, R. W. Schaefer
Nuclear Science and Engineering | Volume 87 | Number 3 | July 1984 | Pages 314-332
Technical Paper | doi.org/10.13182/NSE84-A17785
Use of Integral Experiments in the Assessment of Large Liquid-Metal Fast Breeder Reactor Basic Design Parameters
G. Palmiotti, M. Salvatores
Nuclear Science and Engineering | Volume 87 | Number 3 | July 1984 | Pages 333-348
Technical Paper | doi.org/10.13182/NSE87-333

Number 4

Table of Contents
Introductory Nuclear Reactor Statics (Bernard I. Spinrad)
Before It's Too Late, A Scientist's Case for Nuclear Energy (Manson Benedict)
Comment on a Sensitivity Coefficient in Depletion Perturbation Theory (Nicolaos J. Siakavellas)
Reply to “Comment on a Sensitivity Coefficient in Depletion Perturbation Theory” (M. L. Williams)
Analysis of Finite Difference Approximation in a Discrete Ordinates Transport Equation in One-Dimensional Plane Geometry (V. Sundararaman, R. Vaidyanathan)
Response Matrix of Symmetric Nodes (M. Makai)

Analytical Models for Simulating Hydrogen Transport in Reactor Containment Atmospheres
Vincent P. Manno, Michael W. Golay, Kang Y. Huh
Nuclear Science and Engineering | Volume 87 | Number 4 | August 1984 | Pages 349-360
Technical Paper | doi.org/10.13182/NSE84-A18504
Core-Management Analysis of the Fugen Heavy-Water-Moderated Plutonium-Uranium Mixed Oxide Reactor
Hidemasa Kato, Tohru Haga, Shigeru Ohteru, Hiroshi Kamikawa
Nuclear Science and Engineering | Volume 87 | Number 4 | August 1984 | Pages 361-380
Technical Paper | doi.org/10.13182/NSE84-A18505
Measurements of the Energy Dependence of Prompt Neutron Emission from ²³³U, ²³⁵U, ²³⁹Pu, and ²⁴¹Pu for E_n = 0.005 to 10 eV Relative to Emission from Spontaneous Fission of ²⁵²Cf
R. Gwin, R. R. Spencer, R. W. Ingle
Nuclear Science and Engineering | Volume 87 | Number 4 | August 1984 | Pages 381-404
Technical Paper | doi.org/10.13182/NSE84-A18506
Release of Fission Products from Irradiated Aluminide Fuel at High Temperatures
Toshikazu Shibata, Tadaharu Tamai, Masatoshi Hayashi, John C. Posey, James L. Snelgrove
Nuclear Science and Engineering | Volume 87 | Number 4 | August 1984 | Pages 405-417
Technical Paper | doi.org/10.13182/NSE84-A18507
Evaluation of Delayed-Neutron Emission Probabilities
F. M. Mann, M. Schreiber, R. E. Schenter T. R. England
Nuclear Science and Engineering | Volume 87 | Number 4 | August 1984 | Pages 418-431
Technical Paper | doi.org/10.13182/NSE84-A18508
Analysis of Neutron Yields from High-Energy Proton Bombardment of Uranium Targets
H. Takahashi
Nuclear Science and Engineering | Volume 87 | Number 4 | August 1984 | Pages 432-443
Technical Paper | doi.org/10.13182/NSE84-A18509
Screening Sensitivity Theory
E. M. Oblow, F. G. Perey
Nuclear Science and Engineering | Volume 87 | Number 4 | August 1984 | Pages 444-453
Technical Paper | doi.org/10.13182/NSE84-A18510
Application of an Exact Model Matching Technique to Coupled-Core Nuclear Reactor Control
S. G. Tzafestas, N. G. Chrysochoides, K. Rokkos
Nuclear Science and Engineering | Volume 87 | Number 4 | August 1984 | Pages 454-460
Technical Note | doi.org/10.13182/NSE84-A18511
Optimization of the Fuel Cell of a Spectral Shift Controlled Reactor
F. Alcalá
Nuclear Science and Engineering | Volume 87 | Number 4 | August 1984 | Pages 460-469
Technical Note | doi.org/10.13182/NSE84-A18512
Anisotropic Turbulent Flow in Rod Bundles
M. Abdelghany, M. C. Roco
Nuclear Science and Engineering | Volume 87 | Number 4 | August 1984 | Pages 469-478
Technical Note | doi.org/10.13182/NSE84-A18513
Buildup Factors of Gamma Rays Including Bremsstrahlung and Annihilation Radiation for Water, Concrete, Iron, and Lead
Kiyoshi Takeuchi, Shun-ichi Tanaka
Nuclear Science and Engineering | Volume 87 | Number 4 | August 1984 | Pages 478-489
Technical Note | doi.org/10.13182/NSE84-A18514
On Statistical Identification of Important Input Variables to Large Codes
Jussi K. Vaurio
Nuclear Science and Engineering | Volume 87 | Number 4 | August 1984 | Pages 490-495
Technical Note | doi.org/10.13182/NSE84-A18515