ANS / Publications / Journals / Nuclear Science and Engineering

The International Criticality Safety Benchmark Evaluation Project

J. Blair Briggs, Lori Scott, Ali Nouri

Nuclear Science and Engineering / Volume 145 / Number 1 / September 2003 / Pages 1-10

Technical Paper / dx.doi.org/10.13182/NSE03-14

DICE: Database for the International Criticality Safety Benchmark Evaluation Program Handbook

Ali Nouri, Pierre Nagel, J. Blair Briggs, Tatiana Ivanova

Nuclear Science and Engineering / Volume 145 / Number 1 / September 2003 / Pages 11-19

Technical Paper / dx.doi.org/10.13182/NSE03-15

The Benchmark Evaluation Process: From Experimental Data to Benchmark Model

Virginia A. F. Dean

Nuclear Science and Engineering / Volume 145 / Number 1 / September 2003 / Pages 20-38

Technical Paper / dx.doi.org/10.13182/NSE03-16

Criticality Experiments Performed in Saclay and Valduc Centers, France (1958-2002)

F. Barbry, P. Grivot, E. Girault, P. Fouillaud, P. Cousinou, G. Poullot, J. Anno, J. M. Bordy, D. Doutriaux

Nuclear Science and Engineering / Volume 145 / Number 1 / September 2003 / Pages 39-63

Technical Paper / dx.doi.org/10.13182/NSE03-A2362

A Historical Review of Critical Experiment Research Facilities in the United Kingdom

D. N. Simister, P. D. Clemson

Nuclear Science and Engineering / Volume 145 / Number 1 / September 2003 / Pages 64-71

Technical Paper / dx.doi.org/10.13182/NSE03-A2363

Critical Experiment Programs at the Los Alamos National Laboratory in Support of the U.S. Department of Energy/National Nuclear Security Administration's Nuclear Criticality Safety Program

Steven D. Clement

Nuclear Science and Engineering / Volume 145 / Number 1 / September 2003 / Pages 72-83

Technical Paper / dx.doi.org/10.13182/NSE03-A2364

Criticality Safety Benchmark Experiments Derived from Argonne National Laboratory Zero Power Reactor Assemblies

R. W. Schaefer, R. M. Lell, R. D. McKnight

Nuclear Science and Engineering / Volume 145 / Number 1 / September 2003 / Pages 84-96

Technical Paper / dx.doi.org/10.13182/NSE03-A2365

Influence of the Correlations of Experimental Uncertainties on Criticality Prediction

T. T. Ivanova, M. N. Nikolaev, K. F. Raskach, E. V. Rozhikhin, A. M. Tsiboulia

Nuclear Science and Engineering / Volume 145 / Number 1 / September 2003 / Pages 97-104

Technical Paper / dx.doi.org/10.13182/NSE03-27

Analysis of the First Three Zeus Critical Experiments

Russell D. Mosteller, Roger W. Brewer, Peter J. Jaegers

Nuclear Science and Engineering / Volume 145 / Number 1 / September 2003 / Pages 105-119

Technical Paper / dx.doi.org/10.13182/NSE03-A2367

Use of International Criticality Safety Benchmark Evaluation Project Data to Benchmark a JEF2.2-Based Library for MONK

David Hanlon, Nigel Smith, Jim Gulliford

Nuclear Science and Engineering / Volume 145 / Number 1 / September 2003 / Pages 120-131

Technical Paper / dx.doi.org/10.13182/NSE03-A2368

Validating JENDL-3.3 for Water-Reflected Low-Enriched Uranium Solution Systems Using STACY ICSBEP Benchmark Models

Toshihiro Yamamoto, Yoshinori Miyoshi, Takehide Kiyosumi

Nuclear Science and Engineering / Volume 145 / Number 1 / September 2003 / Pages 132-144

Technical Paper / dx.doi.org/10.13182/NSE03-A2369

Research Reactor Benchmarks

Matjaz Ravnik, Robert Jeraj

Nuclear Science and Engineering / Volume 145 / Number 1 / September 2003 / Pages 145-152

Technical Paper / dx.doi.org/10.13182/NSE03-A2370

Use of International Criticality Safety Benchmark Evaluation Project Benchmarks for the Validation of CSAS26 (Scale 4.4a) for Configurations of Low-Enriched Uranium

Óscar Zurrón, Guillermo Sánchez, Carolina Álvaro

Nuclear Science and Engineering / Volume 145 / Number 1 / September 2003 / Pages 153-159

Technical Paper / dx.doi.org/10.13182/NSE03-A2371

The Critical Mass Laboratory at Rocky Flats

Robert E. Rothe

Nuclear Science and Engineering / Volume 145 / Number 2 / October 2003 / Pages 161-172

Technical Paper / dx.doi.org/10.13182/NSE03-A2372

A Brief History of the Lawrence Radiation Laboratory Criticality Facility

David P. Heinrichs, Stephen C. Wofford

Nuclear Science and Engineering / Volume 145 / Number 2 / October 2003 / Pages 173-180

Technical Paper / dx.doi.org/10.13182/NSE03-A2373

Programs of Experiments with Critical Assemblies at the Russian Research Centre "Kurchatov Institute"

A. A. Bykov, A. Yu. Gagarinski, E. S. Glushkov, Yu. A. Kravchenko, N. E. Kukharkin, D. Pavlov, N. N. Ponomarev-Stepnoi

Nuclear Science and Engineering / Volume 145 / Number 2 / October 2003 / Pages 181-187

Technical Paper / dx.doi.org/10.13182/NSE03-A2374

Benchmark Experiments at VNIITF Test Facilities for Verification of Nuclear Data Libraries

A. P. Vasiliev, Yu. A. Sokolov, V. A. Terekhin, Yu. I. Chernukhin, A. V. Lukin, A. I. Saukov, B. I. Sukhanov, A. M. Ryabinin

Nuclear Science and Engineering / Volume 145 / Number 2 / October 2003 / Pages 188-195

Technical Paper / dx.doi.org/10.13182/NSE03-A2375

Use of Sensitivity and Uncertainty Analysis to Select Benchmark Experiments for the Validation of Computer Codes and Data

K. R. Elam, B. T. Rearden

Nuclear Science and Engineering / Volume 145 / Number 2 / October 2003 / Pages 196-212

Technical Paper / dx.doi.org/10.13182/NSE03-A2376

Monte Carlo Eigenvalue Calculations with ENDF/B-VI.8, JEFF-3.0, and JENDL-3.3 Cross Sections for a Selection of International Criticality Safety Benchmark Evaluation Project Handbook Benchmarks

A. C. Kahler

Nuclear Science and Engineering / Volume 145 / Number 2 / October 2003 / Pages 213-224

Technical Paper / dx.doi.org/10.13182/NSE03-A2377

Criticality Safety of Low-Enriched Uranium and High-Enriched Uranium Fuel Elements in Heavy Water Lattices

Milan P. Pesic

Nuclear Science and Engineering / Volume 145 / Number 2 / October 2003 / Pages 225-233

Technical Paper / dx.doi.org/10.13182/NSE03-A2378

Use of International Criticality Safety Benchmark Evaluation Project Data for Validation of the Nuclear Data Library BAS

V. M. Shmakov, V. D. Lyutov, V. A. Bekhterev

Nuclear Science and Engineering / Volume 145 / Number 2 / October 2003 / Pages 234-246

Technical Paper / dx.doi.org/10.13182/NSE03-A2379

Use of International Criticality Safety Benchmark Evaluation Project Data for Validation of the ABBN Cross-Section Library with the MMK-KENO Code

T. T. Ivanova, M. N. Nikolaev, K. F. Raskach, E. V. Rozhikhin, A. M. Tsiboulia

Nuclear Science and Engineering / Volume 145 / Number 2 / October 2003 / Pages 247-255

Technical Paper / dx.doi.org/10.13182/NSE03-35

Examination of the 2×2 SiO₂, Al, and Fe Experiments Mixed with Highly Enriched Uranium on the Thermal Energy Region

David J. Loaiza, Rene Sanchez

Nuclear Science and Engineering / Volume 145 / Number 2 / October 2003 / Pages 256-266

Technical Paper / dx.doi.org/10.13182/NSE03-A2381

Validation of the Continuous-Energy Monte Carlo Criticality-Safety Analysis System MVP and JENDL-3.2 Using the Internationally Evaluated Criticality Benchmarks

Susumu Mitake

Nuclear Science and Engineering / Volume 145 / Number 2 / October 2003 / Pages 267-277

Technical Paper / dx.doi.org/10.13182/NSE03-A2382

Autocorrelation and Dominance Ratio in Monte Carlo Criticality Calculations

Taro Ueki, Forrest B. Brown, D. Kent Parsons, Drew E. Kornreich

Nuclear Science and Engineering / Volume 145 / Number 3 / November 2003 / Pages 279-290

Technical Paper / dx.doi.org/10.13182/NSE03-04

Convergence Improvement of Response Matrix Method with Large Discontinuity Factors

Akio Yamamoto

Nuclear Science and Engineering / Volume 145 / Number 3 / November 2003 / Pages 291-298

Technical Paper / dx.doi.org/10.13182/NSE03-A2384

DORT-TD: A Transient Neutron Transport Code with Fully Implicit Time Integration

Andreas Pautz, Adolf Birkhofer

Nuclear Science and Engineering / Volume 145 / Number 3 / November 2003 / Pages 299-319

Technical Paper / dx.doi.org/10.13182/NSE03-A2385

Coupling of Time-Dependent Neutron Transport Theory with the Thermal Hydraulics Code ATHLET and Application to the Research Reactor FRM-II

Andreas Pautz, Adolf Birkhofer

Nuclear Science and Engineering / Volume 145 / Number 3 / November 2003 / Pages 320-341

Technical Paper / dx.doi.org/10.13182/NSE03-A2386

Evaluation of Data with Systematic Errors

F. H. Fröhner

Nuclear Science and Engineering / Volume 145 / Number 3 / November 2003 / Pages 342-353

Technical Paper / dx.doi.org/10.13182/NSE03-A2387

Radiological Assessment of Target Materials for Accelerator Transmutation of Waste Applications

Linda D. Vickers

Nuclear Science and Engineering / Volume 145 / Number 3 / November 2003 / Pages 354-375

Technical Paper / dx.doi.org/10.13182/NSE03-A2388

Using NJOY99 and MCNP4B2 to Estimate the Radiation Damage Displacements per Atom per Second in Steel Within the Boiling Water Reactor Core Shroud and Vessel Wall from Reactor-Grade Mixed-Oxide/Uranium Oxide Fuel for the Nuclear Power Plant at Laguna Verde, Veracruz, Mexico

Lisa Vickers

Nuclear Science and Engineering / Volume 145 / Number 3 / November 2003 / Pages 376-389

Technical Paper / dx.doi.org/10.13182/NSE03-A2389

Definition and Application of Proton Source Efficiency in Accelerator-Driven Systems

Per Seltborg, Jan Wallenius, Kamil Tucek, Waclaw Gudowski

Nuclear Science and Engineering / Volume 145 / Number 3 / November 2003 / Pages 390-399

Technical Paper / dx.doi.org/10.13182/NSE03-A2390