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Volume 148

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Number 1

Development of a Method for Measuring the Moderator Temperature Coefficient by Noise Analysis and Its Experimental Verification in Ringhals-2

C. Demazière, I. Pázsit

Nuclear Science and Engineering / Volume 148 / Number 1 / September 2004 / Pages 1-29

Technical Paper

Calculating Probability Tables for the Unresolved-Resonance Region Using Monte Carlo Methods

M. E. Dunn, L. C. Leal

Nuclear Science and Engineering / Volume 148 / Number 1 / September 2004 / Pages 30-42

Technical Paper

Statistical Assignment of Neutron Orbital Angular Momentum to a Resonance

Soo-Youl Oh, Jonghwa Chang, Luiz C. Leal

Nuclear Science and Engineering / Volume 148 / Number 1 / September 2004 / Pages 43-49

Technical Paper

An Interpretation of Energy Dependence of Delayed Neutron Yields in the Resonance Region for 235U and 239Pu

Takaaki Ohsawa, Franz-Josef Hambsch

Nuclear Science and Engineering / Volume 148 / Number 1 / September 2004 / Pages 50-54

Technical Paper

On the Neutron Kinetics and Control of Accelerator-Driven Systems

D. G. Cacuci

Nuclear Science and Engineering / Volume 148 / Number 1 / September 2004 / Pages 55-66

Technical Paper

Theory and Analysis of the Feynman-Alpha Method for Deterministically and Randomly Pulsed Neutron Sources

I. Pázsit, M. Ceder, Z. Kuang

Nuclear Science and Engineering / Volume 148 / Number 1 / September 2004 / Pages 67-78

Technical Paper

Application of the Multipoint Method to the Kinetics of Accelerator-Driven Systems

P. Ravetto, M. M. Rostagno, G. Bianchini, M. Carta, A. D'Angelo

Nuclear Science and Engineering / Volume 148 / Number 1 / September 2004 / Pages 79-88

Technical Paper / dx.doi.org/10.13182/NSE02-10D

Transport Effects for Source-Oscillated Problems in Subcritical Systems

S. Dulla, P. Ravetto, M. M. Rostagno

Nuclear Science and Engineering / Volume 148 / Number 1 / September 2004 / Pages 89-102

Technical Paper

Neutronic Analyses of the Trade Demonstration Facility

C. Rubbia, M. Carta, N. Burgio, C. Ciavola, A. D'Angelo, A. Dodaro, A. Festinesi, S. Monti, A. Santagata, F. Troiani, M. Salvatores, M. Delpech, Y. Kadi, S. Buono, A. Ferrari, A. Herrera Martínez, L. Zanini, G. Imel

Nuclear Science and Engineering / Volume 148 / Number 1 / September 2004 / Pages 103-123

Technical Paper

Neutronic Studies in Support of Accelerator-Driven Systems: The MUSE Experiments in the MASURCA Facility

R. Soule, W. Assal, P. Chaussonnet, C. Destouches, C. Domergue, C. Jammes, J.-M. Laurens, J.-F. Lebrat, F. Mellier, G. Perret, G. Rimpault, H. Servière, G. Imel, G. M. Thomas, D. Villamarin, E. Gonzalez-Romero, M. Plaschy, R. Chawla, J. L. Kloosterman, Y. Rugama, A. Billebaud, R. Brissot, D. Heuer, M. Kerveno, C. Le Brun, E. Liatard, J.-M. Loiseaux, O. Méplan, E. Merle, F. Perdu, J. Vollaire, P. Baeten

Nuclear Science and Engineering / Volume 148 / Number 1 / September 2004 / Pages 124-152

Technical Paper / dx.doi.org/10.13182/NSE01-13C

A Receding Horizon Controller with a Parameter Estimator for Nuclear Reactor Power Distribution

Man Gyun Na, Dong Won Jung, Sun Mi Lee

Nuclear Science and Engineering / Volume 148 / Number 1 / September 2004 / Pages 153-161

Technical Paper

Development and Application of a Decomposition Methodology for Interpretation of Reactivity Effect Discrepancies

R. van Geemert, F. Jatuff, F. Tani, R. Chawla

Nuclear Science and Engineering / Volume 148 / Number 1 / September 2004 / Pages 162-171

Technical Paper

RTk/SN Solutions of the Two-Dimensional Multigroup Transport Equations in Hexagonal Geometry

Edmundo del Valle, Ernest H. Mund

Nuclear Science and Engineering / Volume 148 / Number 1 / September 2004 / Pages 172-185

Technical Paper

A Second-Order Finite Volume Discretization of the Time-Dependent Transport Equation on Arbitrary Quadrilaterals in R-Z Geometry

Alexander V. Voronkov, Elena P. Sychugova

Nuclear Science and Engineering / Volume 148 / Number 1 / September 2004 / Pages 186-194

Technical Paper

Number 2

OECD/NRC BWR Turbine Trip Transient Benchmark as a Basis for Comprehensive Qualification and Studying Best-Estimate Coupled Codes

Kostadin Ivanov, Andy Olson, Enrico Sartori

Nuclear Science and Engineering / Volume 148 / Number 2 / October 2004 / Pages 195-207

Technical Paper

Application of TRAC/BF1-ENTRÉE-NASCA to OECD NEA/NSC BWR Turbine Trip Benchmark

Akitoshi Hotta, Minyan Zhang, Hiroshi Shirai

Nuclear Science and Engineering / Volume 148 / Number 2 / October 2004 / Pages 208-225

Technical Paper

Analysis of the Boiling Water Reactor Turbine Trip Benchmark with the Codes DYN3D and ATHLET/DYN3D

Ulrich Grundmann, Sören Kliem, Ulrich Rohde

Nuclear Science and Engineering / Volume 148 / Number 2 / October 2004 / Pages 226-234

Technical Paper

Computation of a BWR Turbine Trip with CATHARE-CRONOS2-FLICA4 Coupled Codes

G. Mignot, E. Royer, B. Rameau, N. Todorova

Nuclear Science and Engineering / Volume 148 / Number 2 / October 2004 / Pages 235-246

Technical Paper

OECD/NRC BWR Turbine Trip Benchmark: Simulation by POLCA-T Code

Dobromir Panayotov

Nuclear Science and Engineering / Volume 148 / Number 2 / October 2004 / Pages 247-255

Technical Paper

Peach Bottom Transients Analysis with TRAC/BF1-VALKIN

G. Verdú, R. Miró, A. M. Sánchez, O. Roselló, D. Ginestar, V. Vidal

Nuclear Science and Engineering / Volume 148 / Number 2 / October 2004 / Pages 256-269

Technical Paper

Analysis of the OECD/NRC BWR Turbine Trip Benchmark by the Coupled-Code System ATHLET-QUABOX/CUBBOX

S. Langenbuch, K.-D. Schmidt, K. Velkov

Nuclear Science and Engineering / Volume 148 / Number 2 / October 2004 / Pages 270-280

Technical Paper

Peach Bottom 2 Turbine Trip Simulation Using TRAC-BF1/COS3D, a Best-Estimate Coupled 3-D Core and Thermal-Hydraulic Code System

Atsushi Ui, Takamasa Miyaji

Nuclear Science and Engineering / Volume 148 / Number 2 / October 2004 / Pages 281-290

Technical Paper

Analysis of the OECD/NRC BWR Turbine Trip Transient Benchmark with the Coupled Thermal-Hydraulics and Neutronics Code TRAC-M/PARCS

Deokjung Lee, Thomas J. Downar, Anthony Ulses, Bedirhan Akdeniz, Kostadin N. Ivanov

Nuclear Science and Engineering / Volume 148 / Number 2 / October 2004 / Pages 291-305

Technical Paper

Peach Bottom BWR Turbine Trip Benchmark Analyses with RETRAN-3D and CORETRAN

W. Barten, H. Ferroukhi, P. Coddington

Nuclear Science and Engineering / Volume 148 / Number 2 / October 2004 / Pages 306-324

Technical Paper

SIMULATE-3K Peach Bottom 2 Turbine Trip 2 Benchmark Calculations

Lotfi A. Belblidia, Gerardo M. Grandi, Christian Jönsson

Nuclear Science and Engineering / Volume 148 / Number 2 / October 2004 / Pages 325-336

Technical Paper

Analysis of the Peach Bottom Turbine Trip 2 Experiment by Coupled RELAP5-PARCS Three-Dimensional Codes

Anis Bousbia-Salah, Juswald Vedovi, Francesco D'Auria, Kostadin Ivanov, Giorgio Galassi

Nuclear Science and Engineering / Volume 148 / Number 2 / October 2004 / Pages 337-353

Technical Paper

Number 3

Coarse-Mesh Angular Dependent Rebalance Acceleration of the Discrete Ordinates Transport Calculations

Young Ryong Park, Nam Zin Cho

Nuclear Science and Engineering / Volume 148 / Number 3 / November 2004 / Pages 355-373

Technical Paper / dx.doi.org/10.13182/NSE03-12

Time Series Analysis of Monte Carlo Fission Sources - I: Dominance Ratio Computation

Taro Ueki, Forrest B. Brown, D. Kent Parsons, James S. Warsa

Nuclear Science and Engineering / Volume 148 / Number 3 / November 2004 / Pages 374-390

Technical Paper / dx.doi.org/10.13182/NSE03-95

Ex Post Facto Monte Carlo Variance Reduction

Thomas E. Booth

Nuclear Science and Engineering / Volume 148 / Number 3 / November 2004 / Pages 391-402

Technical Paper

An Analytical Study of Particle Transport in Spatially Random Media in One Dimension: Mean and Variance Calculations

A. Z. Akcasu, M. M. R. Williams

Nuclear Science and Engineering / Volume 148 / Number 3 / November 2004 / Pages 403-413

Technical Paper

Development of Pressurized Water Reactor Integrated Safety Analysis Methodology Using Multilevel Coupling Algorithm

Dmitri Ziabletsev, Maria Avramova, Kostadin Ivanov

Nuclear Science and Engineering / Volume 148 / Number 3 / November 2004 / Pages 414-425

Technical Paper

Development of a Unique Curve for Thermal Neutron Self-Shielding Factor in Spherical Scattering Materials

J. Salgado, I. F. Gonçalves, E. Martinho

Nuclear Science and Engineering / Volume 148 / Number 3 / November 2004 / Pages 426-428

Technical Paper

Time-Varying Characteristics Analysis and Fuzzy Controller Systematic Design Method for Pressurized Water Reactor Power Control

Shengzhi Liu, Naiyao Zhang, Zhenhua Cui

Nuclear Science and Engineering / Volume 148 / Number 3 / November 2004 / Pages 429-444

Technical Paper

Collision Integral Cross Sections in Double Photon Compton Scattering and a Possible Method for Their Measurement

Aarti Sharma, M. B. Saddi, B. Singh, B. S. Sandhu

Nuclear Science and Engineering / Volume 148 / Number 3 / November 2004 / Pages 445-452

Technical Paper

The Thermal Diffusion Length Problem in an Array of Plates

J. S. Cassell, M. M. R. Williams

Nuclear Science and Engineering / Volume 148 / Number 3 / November 2004 / Pages 453-457

Technical Note

Resource Note on Photofission of Nuclei for 235U and 239Pu Detection

Michael Martin Nieto

Nuclear Science and Engineering / Volume 148 / Number 3 / November 2004 / Pages 458-461

Technical Note

 
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