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Volume 98

Number 1 | Number 2 | Number 3 | Number 4

Number 1

Hydrogen Generation During Fuel/Coolant Interactions

M. F. Young, L. T. Pong

Nuclear Science and Engineering / Volume 98 / Number 1 / January 1988 / Pages 1-15

Technical Paper / dx.doi.org/10.13182/NSE88-A23521

Modeling of Small-Scale Single Droplet Fuel/Coolant Interactions

B. Kim, M. L. Corradini

Nuclear Science and Engineering / Volume 98 / Number 1 / January 1988 / Pages 16-28

Technical Paper / dx.doi.org/10.13182/NSE88-A23522

The Weighted Diamond-Difference Form of Nodal Transport Methods

Y. Y. Azmy

Nuclear Science and Engineering / Volume 98 / Number 1 / January 1988 / Pages 29-40

Technical Paper / dx.doi.org/10.13182/NSE88-6

Discrete Elements Method of Neutron Transport

Kirk A. Mathews

Nuclear Science and Engineering / Volume 98 / Number 1 / January 1988 / Pages 41-50

Technical Paper / dx.doi.org/10.13182/NSE98-01-41

A New Direction Biasing Approach for Monte Carlo Simulation

R. P. Gardner, M. Mickael, K. Verghese

Nuclear Science and Engineering / Volume 98 / Number 1 / January 1988 / Pages 51-63

Technical Paper / dx.doi.org/10.13182/NSE88-A23525

GO-FLOW: A New Reliability Analysis Methodology

Takeshi Matsuoka, Michiyuki Kobayashi

Nuclear Science and Engineering / Volume 98 / Number 1 / January 1988 / Pages 64-78

Technical Paper / dx.doi.org/10.13182/NSE88-A23526

Core-Melt Probability Update

H. W. Lewis

Nuclear Science and Engineering / Volume 98 / Number 1 / January 1988 / Pages 79-81

Technical Paper / dx.doi.org/10.13182/NSE88-A23527

Applications of the Generalized Bias Operator for Uncertainty Analysis

Yigal Ronen

Nuclear Science and Engineering / Volume 98 / Number 1 / January 1988 / Pages 82-86

Technical Paper / dx.doi.org/10.13182/NSE88-A23528

Number 2

Application of the “Reactivity Constraint Approach” to Automatic Reactor Control

John A. Bernard, Allan F. Henry, David D. Lanning

Nuclear Science and Engineering / Volume 98 / Number 2 / February 1988 / Pages 87-96

Technical Paper / dx.doi.org/10.13182/NSE88-A28488

Reactor Sensor Surveillance Using Noise Analysis

H. M. Hashemian, J. A. Thie, B. R. Upadhyaya

Nuclear Science and Engineering / Volume 98 / Number 2 / February 1988 / Pages 96-102

Technical Paper / dx.doi.org/10.13182/NSE88-A28489

Spatial Kinetics Studies in Liquid-Metal Fast Breeder Reactor Critical Assemblies

S. B. Brumbach, R. W. Goin, S. G. Carpenter

Nuclear Science and Engineering / Volume 98 / Number 2 / February 1988 / Pages 103-117

Technical Paper / dx.doi.org/10.13182/NSE88-A28490

An Improved Cell Calculation Method for Liquid-Metal Fast Breeder Reactor Blanket Analysis

Keisho Shirakata, Toshihisa Yamamoto, Toshikazu Takeda, Hironobu Unesaki

Nuclear Science and Engineering / Volume 98 / Number 2 / February 1988 / Pages 118-127

Technical Paper / dx.doi.org/10.13182/NSE88-A28491

Two-Dimensional Cell Heterogeneity Effect in Analysis of Fast Critical Assemblies

Toshikazu Takeda, Hironobu Unesaki, Toshihisa Yamamoto, Keisho Shirakata

Nuclear Science and Engineering / Volume 98 / Number 2 / February 1988 / Pages 128-137

Technical Paper / dx.doi.org/10.13182/NSE88-A28492

Calculation of Three-Dimensional Flux Distributions in CANDU Reactors Using Lattice Properties Dependent on Several Local Parameters

B. Rouben, K. S. Brunner, D. A. Jenkins

Nuclear Science and Engineering / Volume 98 / Number 2 / February 1988 / Pages 139-148

Technical Paper / dx.doi.org/10.13182/NSE88-A28493

Impact of Moderator History on Physics Parameters in Pressurized Water Reactors

R. D. Mosteller

Nuclear Science and Engineering / Volume 98 / Number 2 / February 1988 / Pages 149-153

Technical Paper / dx.doi.org/10.13182/NSE88-A28494

Analysis of the Rancho Seco Overcooling Event Using PCTRAN, the Personal Computer Transient Analyzer

Li-Chi Cliff Po

Nuclear Science and Engineering / Volume 98 / Number 2 / February 1988 / Pages 154-161

Technical Paper / dx.doi.org/10.13182/NSE88-A28495

Standard Problem Calculations with BALO-2A

G. Sdouz

Nuclear Science and Engineering / Volume 98 / Number 2 / February 1988 / Pages 162-168

Technical Paper / dx.doi.org/10.13182/NSE88-A28496

Wielandt Iteration as Applied to the Nodal Expansion Method

T. M. Sutton

Nuclear Science and Engineering / Volume 98 / Number 2 / February 1988 / Pages 169-173

Technical Paper / dx.doi.org/10.13182/NSE88-1

Prompt Neutron Emission Multiplicity Distribution and Average Values (Nubar) at 2200 m/s for the Fissile Nuclides

Norman E. Holden, Martin S. Zucker

Nuclear Science and Engineering / Volume 98 / Number 2 / February 1988 / Pages 174-181

Technical Paper / dx.doi.org/10.13182/NSE88-A28498

Number 3

Analysis of Thermal Tests in a Pressurized Water Reactor Having Asymmetric Loop Flows

R. W. Lyczkowski, J. H. Kim, H. P. Fohs, H. M. Domanus

Nuclear Science and Engineering / Volume 98 / Number 3 / March 1988 / Pages 183-208

Technical Paper / dx.doi.org/10.13182/NSE88-A22322

Coolant Recirculation in a Pressurized Water Reactor Core Under Loss-of-Coolant Accident Conditions

M. K. Moallemi, R. Viskanta

Nuclear Science and Engineering / Volume 98 / Number 3 / March 1988 / Pages 209-225

Technical Paper / dx.doi.org/10.13182/NSE88-A22323

Effectiveness of a Consistently Formulated Diffusion-Synthetic Acceleration Differencing Approach

Hussein Khalil

Nuclear Science and Engineering / Volume 98 / Number 3 / March 1988 / Pages 226-243

Technical Paper / dx.doi.org/10.13182/NSE88-A22324

Accuracy of the Modal-Local Method for Reactivity Determination

João Moreira, John C. Lee

Nuclear Science and Engineering / Volume 98 / Number 3 / March 1988 / Pages 244-254

Technical Paper / dx.doi.org/10.13182/NSE88-A22325

The Periodic Dependence of Fission-Fragment Ranges on the Target Atomic Number Z2

P. Dickstein, D. Ingman, N. H. Shafrir

Nuclear Science and Engineering / Volume 98 / Number 3 / March 1988 / Pages 255-265

Technical Paper / dx.doi.org/10.13182/NSE88-A22326

Experimentally Determined Excitation Function for the 9Be(n,t) Reaction

H. Liskien, R. Widera, R. Wölfle, S. M. Qaim

Nuclear Science and Engineering / Volume 98 / Number 3 / March 1988 / Pages 266-271

Technical Note / dx.doi.org/10.13182/NSE88-A22327

Radiation Shielding Calculations for a 70- to 250-MeV Proton Therapy Facility

W. K. Hagan, B. L. Colborn, T. W. Armstrong, M. Allen

Nuclear Science and Engineering / Volume 98 / Number 3 / March 1988 / Pages 272-278

Technical Note / dx.doi.org/10.13182/NSE88-A22328

Number 4

Discrete Angle Biasing in Monte Carlo Radiation Transport

S. N. Cramer

Nuclear Science and Engineering / Volume 98 / Number 4 / April 1988 / Pages 279-298

Technical Paper / dx.doi.org/10.13182/NSE88-A23530

On the Efficiency of Generalized Antithetic Transformations for Monte Carlo Integration

John H. Halton

Nuclear Science and Engineering / Volume 98 / Number 4 / April 1988 / Pages 299-316

Technical Paper / dx.doi.org/10.13182/NSE88-A23531

Improvements of the Electric Field Correction in Recoil-Proton Detectors

R. T. Couto, K. O. Ott, F. M. Clikeman

Nuclear Science and Engineering / Volume 98 / Number 4 / April 1988 / Pages 317-325

Technical Paper / dx.doi.org/10.13182/NSE88-A23532

Spatial Eigenfunctions, Time Eigenvalues, and Leakage Currents of Two-Region (Grooved) Neutron Moderators

John M. Carpenter, Yasushi F. Taked, David F. R. Mildner

Nuclear Science and Engineering / Volume 98 / Number 4 / April 1988 / Pages 326-340

Technical Paper / dx.doi.org/10.13182/NSE88-A23533

Search for an Energy Dependence in 235U Delayed Neutron Spectra

Q. Sharfuddin, W. A. Schier, R. S. Tanczyn, D. J. Pullen, M. H. Haghighi, L. Fisteag, G. P. Couchell

Nuclear Science and Engineering / Volume 98 / Number 4 / April 1988 / Pages 341-347

Technical Paper / dx.doi.org/10.13182/NSE88-A23534

Photon Production Cross Section for 181 Ta

P. Ramakrishnan, G. E. Mitchell, C. R. Gould, S. A. Wender and G. F. Auchampaugh

Nuclear Science and Engineering / Volume 98 / Number 4 / April 1988 / Pages 348-356

Technical Paper / dx.doi.org/10.13182/NSE88-A23535

Neutron-Induced Photon Production Cross Sections

P. Ramakrishnan, G. E. Mitchell, C. R. Gould, S. A. Wender, G. F. Auchampaugh, R. C. Little

Nuclear Science and Engineering / Volume 98 / Number 4 / April 1988 / Pages 357-364

Technical Paper / dx.doi.org/10.13182/NSE88-A23536