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Volume 87

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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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.doi.org/10.13182/NSE84-A18515