ANS / Publications / Journals / Nuclear Science and Engineering

Weapons-Grade Plutonium Disposition in Pressurized Water Reactors

Debdas Biswas, Roy W. Rathbun, Si Young Lee, Melvin R. Buckner

Nuclear Science and Engineering / Volume 121 / Number 1 / September 1995 / Pages 1-16

Technical Paper / dx.doi.org/10.13182/NSE95-A24124

Physics Studies of Weapons Plutonium Disposition in the Integral Fast Reactor Closed Fuel Cycle

R. N. Hill, D. C. Wade, J. R. Liaw, E. K. Fujita

Nuclear Science and Engineering / Volume 121 / Number 1 / September 1995 / Pages 17-31

Technical Paper / dx.doi.org/10.13182/NSE121-17

Optimization of a Calculation Scheme for the Treatment of Plutonium Recycling in Pressurized Water Reactors

Philippe Fougeras, Stéphane Cathalau, Jacques Mondot, Pavel Klenov

Nuclear Science and Engineering / Volume 121 / Number 1 / September 1995 / Pages 32-40

Technical Paper / dx.doi.org/10.13182/NSE121-32

CASMO-4/SIMULATE-3 Benchmarking Against High Plutonium Content Pressurized Water Reactor Mixed-Oxide Fuel Critical Experiment

Masaaki Mori and Mitsuru Kawamura, Koichi Yamate

Nuclear Science and Engineering / Volume 121 / Number 1 / September 1995 / Pages 41-51

Technical Paper / dx.doi.org/10.13182/NSE95-A24127

Analyses of Boiling Water Reactor Mixed-Oxide Critical Experiments with CASMO-4/SIMULATE-3

E. Saji, H. Shirayanagi

Nuclear Science and Engineering / Volume 121 / Number 1 / September 1995 / Pages 52-56

Technical Paper / dx.doi.org/10.13182/NSE95-A24128

Continuing Advancements in In-Core Power Distribution Measurement Methods Using SIMULATE-3 and CECOR 3.4

Charles F. Karlson

Nuclear Science and Engineering / Volume 121 / Number 1 / September 1995 / Pages 57-66

Technical Paper / dx.doi.org/10.13182/NSE95-A24129

Optimization of Pressurized Water Reactor Shuffling by Simulated Annealing with Heuristics

J. G. Stevens, K. S. Smith, K. R. Rempe, T. J. Downar

Nuclear Science and Engineering / Volume 121 / Number 1 / September 1995 / Pages 67-88

Technical Paper / dx.doi.org/10.13182/NSE121-67

Variationally Derived Coarse-Mesh Methods Based on an Alternative Flux Representation

Greg Wojtowicz, James Paul Holloway

Nuclear Science and Engineering / Volume 121 / Number 1 / September 1995 / Pages 89-102

Technical Paper / dx.doi.org/10.13182/NSE95-A24131

Iterative Schemes for Parallel S_n Algorithms in a Shared-Memory Computing Environment

Alireza Haghighat, Melissa A. Hunter, Ronald E. Mattis

Nuclear Science and Engineering / Volume 121 / Number 1 / September 1995 / Pages 103-113

Technical Paper / dx.doi.org/10.13182/NSE95-A24132

New Core-Reflector Boundary Conditions for Transient Nodal Reactor Calculations

Eun Ki Lee and Chang Hyo Kim and Hyung Kook Joo

Nuclear Science and Engineering / Volume 121 / Number 1 / September 1995 / Pages 114-129

Technical Paper / dx.doi.org/10.13182/NSE95-A24133

The Green’s Function Nodal Expansion Method for Light Water Reactor Diffusion Calculations

Wei Shen, Zhongsheng Xie, Banghua Yin

Nuclear Science and Engineering / Volume 121 / Number 1 / September 1995 / Pages 130-135

Technical Paper / dx.doi.org/10.13182/NSE95-A24134

Thermal-Spectrum Recriticality Energetics

K. N. Schwinkendorf

Nuclear Science and Engineering / Volume 121 / Number 1 / September 1995 / Pages 136-141

Technical Paper / dx.doi.org/10.13182/NSE95-A24135

Advanced Designs and Operating Strategies to Enhance the Safety, Operability, and Efficiency of VVER-1000 Reactors

J. R. Seeker, R. W. Miller, L. T. Mayhue, R. N. Milanova

Nuclear Science and Engineering / Volume 121 / Number 1 / September 1995 / Pages 142-152

Technical Paper / dx.doi.org/10.13182/NSE95-A24136

Void Fraction Measurements Using Neutron Radiography

Stanley S. Glickstein, William H. Vance, Hansem Joo

Nuclear Science and Engineering / Volume 121 / Number 1 / September 1995 / Pages 153-161

Technical Paper / dx.doi.org/10.13182/NSE95-A24137

Evaluation of End-of-Cycle Moderator Temperature Coefficient Measurements for Davis-Besse Unit 1

Robert J. Borland

Nuclear Science and Engineering / Volume 121 / Number 1 / September 1995 / Pages 162-171

Technical Paper / dx.doi.org/10.13182/NSE95-A24138

Computation of Continuous-Energy Neutron Spectra with Discrete Ordinates Transport Theory

M. L. Williams, M. Asgari

Nuclear Science and Engineering / Volume 121 / Number 2 / October 1995 / Pages 173-201

Technical Paper / dx.doi.org/10.13182/NSE95-1

Conformal Mapping and Hexagonal Nodal Methods —I: Mathematical Foundation

Y. A. Chao, N. Tsoulfanidis

Nuclear Science and Engineering / Volume 121 / Number 2 / October 1995 / Pages 202-209

Technical Paper / dx.doi.org/10.13182/NSE95-A28558

Conformal Mapping and Hexagonal Nodal Methods —II: Implementation in the ANC-H Code

Y. A. Chao, Y. A. Shatilla

Nuclear Science and Engineering / Volume 121 / Number 2 / October 1995 / Pages 210-225

Technical Paper / dx.doi.org/10.13182/NSE95-A28559

Systematic Homogenization and Self-Consistent Flux and Pin Power Reconstruction for Nodal Diffusion Methods —I: Diffusion Equation-Based Theory

Hongbin Zhang, Rizwan-uddin, J. J. Dorning

Nuclear Science and Engineering / Volume 121 / Number 2 / October 1995 / Pages 226-244

Technical Paper / dx.doi.org/10.13182/NSE95-A28560

Analytic Function Expansion Nodal Method for Hexagonal Geometry

Nam Zin Cho, Jae Man Noh

Nuclear Science and Engineering / Volume 121 / Number 2 / October 1995 / Pages 245-253

Technical Paper / dx.doi.org/10.13182/NSE95-A28561

Comparison of PANTHER Nodal Solutions in Hexagonal-z Geometry

M. Knight, P. Hutt, I. Lewis

Nuclear Science and Engineering / Volume 121 / Number 2 / October 1995 / Pages 254-263

Technical Paper / dx.doi.org/10.13182/NSE95-A28562

Probabilistic Method of Discrete Ordinates in a Neutron Transport Problem

V. Khromov, E. Kryuchkov, G. Tikhomirov, L. Goncharov, V. Kondakov

Nuclear Science and Engineering / Volume 121 / Number 2 / October 1995 / Pages 264-276

Technical Paper / dx.doi.org/10.13182/NSE95-A28563

Parallel Implementation of Integral Transport Methods

Emilio Fuentes, Paul J. Turinsky

Nuclear Science and Engineering / Volume 121 / Number 2 / October 1995 / Pages 277-285

Technical Paper / dx.doi.org/10.13182/NSE95-A28564

Calculational Verification and Process Control Applications Utilizing the High Sensitivity of Noise Measurement Parameters to Fissile System Configuration

J. T. Mihalczo, T. E. Valentine

Nuclear Science and Engineering / Volume 121 / Number 2 / October 1995 / Pages 286-300

Technical Paper / dx.doi.org/10.13182/NSE95-A28565

Fuel-Temperature Coefficient for Boiling Water Reactor Transient Calculations: Its Dependence on Reactor Conditions

John M. Kallfelz, Lotfi A. Belblidia, Peter Grimm

Nuclear Science and Engineering / Volume 121 / Number 2 / October 1995 / Pages 301-311

Technical Paper / dx.doi.org/10.13182/NSE95-A28566

Employing Nodal Generalized Perturbation Theory for the Minimization of Feed Enrichment During Pressurized Water Reactor In-Core Nuclear Fuel Management Optimization

G. Ivan Maldonado, Paul J. Turinsky, David J. Kropaczek,Geoffrey T. Parks

Nuclear Science and Engineering / Volume 121 / Number 2 / October 1995 / Pages 312-325

Technical Paper / dx.doi.org/10.13182/NSE95-A28567

Qualification of the JEF2.2 Cross Sections in the Epithermal and Thermal Energy Ranges Using a Statistical Approach

Stephane Cathalau, Amal Benslimane, Abdelmajid Maghnouj, Philippe Fougeras, Vladimir Ukraintsev

Nuclear Science and Engineering / Volume 121 / Number 2 / October 1995 / Pages 326-333

Technical Paper / dx.doi.org/10.13182/NSE95-A28568

Radiation Streaming Analysis in the Radial and Tangential Beam Tubes of a TRIGA Research Reactor Using MCNP and Comparison with Measurement

Ji Bok Lee, Byong Whie Lee, Byung Chul Lee

Nuclear Science and Engineering / Volume 121 / Number 2 / October 1995 / Pages 334-344

Technical Paper / dx.doi.org/10.13182/NSE95-A28569

Quasi Solution of Radiation Transport Equation

Leonid R. Pogosbekyan, Dmitrij A. Lysov

Nuclear Science and Engineering / Volume 121 / Number 2 / October 1995 / Pages 345-351

Technical Paper / dx.doi.org/10.13182/NSE95-A28570

Variational Estimates of Point-Kinetics Parameters

J. A. Favorite, W. M. Stacey, Jr.

Nuclear Science and Engineering / Volume 121 / Number 3 / December 1995 / Pages 353-370

Technical Paper / dx.doi.org/10.13182/NSE95-A24140

Variational Derivation of Multigroup P₂ Equations and Boundary Conditions in Planar Geometry

Robert P. Rulko

Nuclear Science and Engineering / Volume 121 / Number 3 / December 1995 / Pages 371-392

Technical Paper / dx.doi.org/10.13182/NSE95-A24141

Variational P₁ Approximations of General-Geometry Multigroup Transport Problems

Robert P. Rulko, Djordje Tomašević, Edward W. Larsen

Nuclear Science and Engineering / Volume 121 / Number 3 / December 1995 / Pages 393-404

Technical Paper / dx.doi.org/10.13182/NSE121-393

An Augmented Source Method for the Application of Nodal Equivalence Theory

C. J. Hah, T. J. Downar

Nuclear Science and Engineering / Volume 121 / Number 3 / December 1995 / Pages 405-415

Technical Paper / dx.doi.org/10.13182/NSE95-A24143

Response Matrix Properties and Convergence Implications for an Interface-Current Nodal Formulation

W. S. Yang

Nuclear Science and Engineering / Volume 121 / Number 3 / December 1995 / Pages 416-432

Technical Paper / dx.doi.org/10.13182/NSE95-A24144

Neutron Fluence at the Pressure Vessel of a Pressurized Water Reactor Determined by the MCNP Code

Peter G. Laky, Nicholas Tsoulfanidis

Nuclear Science and Engineering / Volume 121 / Number 3 / December 1995 / Pages 433-447

Technical Paper / dx.doi.org/10.13182/NSE95-A24145

Physics Characteristics of a Large, Passive, Pressure Tube Light Water Reactor with Voided Calandria

Pavel Hejzlar, Michael J. Driscoll, Neil E. Todreas

Nuclear Science and Engineering / Volume 121 / Number 3 / December 1995 / Pages 448-460

Technical Paper / dx.doi.org/10.13182/NSE95-A24146

On the Compartmental Modeling of Cesium Migration in Soils

M. Antonopoulos-Domis, A. Clouvas, M. Marseguerra

Nuclear Science and Engineering / Volume 121 / Number 3 / December 1995 / Pages 461-467

Technical Paper / dx.doi.org/10.13182/NSE95-A24147

Modeling Water Chemistry, Electrochemical Corrosion Potential, and Crack Growth Rate in the Boiling Water Reactor Heat Transport Circuits—I: The DAMAGE-PREDICTOR Algorithm

Tsung-Kuang Yeh, Digby D. Macdonald, Arthur T. Motta

Nuclear Science and Engineering / Volume 121 / Number 3 / December 1995 / Pages 468-482

Technical Paper / dx.doi.org/10.13182/NSE95-A24148

Correlations of the Independent Fission Product Yields of Different Isotopes

Yigal Ronen

Nuclear Science and Engineering / Volume 121 / Number 3 / December 1995 / Pages 483-491

Technical Paper / dx.doi.org/10.13182/NSE95-A24149