American Nuclear Society
Home

Home / Publications / Journals / Nuclear Science and Engineering / Volume 153

Volume 153

Number 1 | Number 2 | Number 3

Number 1

Evaluation and Propagation of the 239Pu Fission Cross-Section Uncertainties Using a Monte Carlo Technique

T. Kawano, K. M. Hanson, S. Frankle, P. Talou, M. B. Chadwick, R. C. Little

Nuclear Science and Engineering / Volume 153 / Number 1 / May 2006 / Pages 1-7

Technical Paper / dx.doi.org/10.13182/NSE06-A2589

Neutron Transmission and Capture Measurements and Resonance Parameter Analysis of Neodymium from 1 to 500 eV

D. P. Barry, M. J. Trbovich, Y. Danon, R. C. Block, R. E. Slovacek, G. Leinweber, J. A. Burke, N. J. Drindak

Nuclear Science and Engineering / Volume 153 / Number 1 / May 2006 / Pages 8-25

Technical Paper / dx.doi.org/10.13182/NSE06-A2590

Calculation of the Prompt Neutron Lifetime in the NBSR

Albert L. Hanson, Hans Ludewig, David J. Diamond

Nuclear Science and Engineering / Volume 153 / Number 1 / May 2006 / Pages 26-32

Technical Paper / dx.doi.org/10.13182/NSE06-4

Photonuclear Physics in Radiation Transport - III: Actinide Cross Sections and Spectra

M.-L. Giacri-Mauborgne, D. Ridikas, M. B. Chadwick, P. G. Young, W. B. Wilson

Nuclear Science and Engineering / Volume 153 / Number 1 / May 2006 / Pages 33-40

Technical Paper / dx.doi.org/10.13182/NSE06-A2592

Differential and Angle-Integrated Cross-Section Measurement for the 6Li(n,t)4He Reaction at En = 1.05, 1.54, and 2.25 MeV

Guohui Zhang, Rongtai Cao, Jinxiang Chen, Guoyou Tang, Yu. M. Gledenov, M. Sedysheva, G. Khuukhenkhuu

Nuclear Science and Engineering / Volume 153 / Number 1 / May 2006 / Pages 41-45

Technical Paper / dx.doi.org/10.13182/NSE153-41

Collision Probabilities in r--z Geometry

R. D. M. Garcia

Nuclear Science and Engineering / Volume 153 / Number 1 / May 2006 / Pages 46-59

Technical Paper / dx.doi.org/10.13182/NSE06-A2594

The Statistics of the Number of Neutron Collisions Prior to Absorption

Sara A. Pozzi, Imre Pázsit

Nuclear Science and Engineering / Volume 153 / Number 1 / May 2006 / Pages 60-68

Technical Paper / dx.doi.org/10.13182/NSE06-A2595

Space-Time Correction for Reactivity Determination in Source-Driven Subcritical Systems

Viktoriya V. Kulik, John C. Lee

Nuclear Science and Engineering / Volume 153 / Number 1 / May 2006 / Pages 69-89

Technical Paper / dx.doi.org/10.13182/NSE06-A2596

The Smallest Thermal Nuclear Reactor

Y. Ronen, E. Fridman, E. Shwageraus

Nuclear Science and Engineering / Volume 153 / Number 1 / May 2006 / Pages 90-92

Technical Paper / dx.doi.org/10.13182/NSE06-A2597

MEND: A Program for Calculating the Complete Set of Nuclear Data of Medium-Heavy Nuclei in a Medium-Low Energy Region

Chong-Hai Cai

Nuclear Science and Engineering / Volume 153 / Number 1 / May 2006 / Pages 93-97

Computer Code Abstract / dx.doi.org/10.13182/NSE05-06CCA

Number 2

Probabilistic Techniques for Diagnosis of Multiple Component Degradations

Steven E. Aumeier, Bulent Alpay, John C. Lee, A. Ziya Akcasu

Nuclear Science and Engineering / Volume 153 / Number 2 / June 2006 / Pages 101-123

Technical Paper / dx.doi.org/10.13182/NSE06-A2599

Estimation of Effective Parameters in a Lumped Nuclear Reactor Model Using Multiobjective Genetic Algorithms

Marzio Marseguerra, Enrico Zio, Raffaele Canetta

Nuclear Science and Engineering / Volume 153 / Number 2 / June 2006 / Pages 124-136

Technical Paper / dx.doi.org/10.13182/NSE06-A2600

MCDET: A Probabilistic Dynamics Method Combining Monte Carlo Simulation with the Discrete Dynamic Event Tree Approach

Martina Kloos, Jörg Peschke

Nuclear Science and Engineering / Volume 153 / Number 2 / June 2006 / Pages 137-156

Technical Paper / dx.doi.org/10.13182/NSE06-A2601

A Fuzzy Logic-Based Model for the Classification of Faults in the Pump Seals of the Primary Heat Transport System of a CANDU 6 Reactor

Marzio Marseguerra, Enrico Zio, Piero Baraldi, Irina Crenguta Popescu, Paul Ulmeanu

Nuclear Science and Engineering / Volume 153 / Number 2 / June 2006 / Pages 157-171

Technical Paper / dx.doi.org/10.13182/NSE06-A2602

Time Series Analysis of Monte Carlo Fission Sources—II: Confidence Interval Estimation

Taro Ueki, Brian R. Nease

Nuclear Science and Engineering / Volume 153 / Number 2 / June 2006 / Pages 184-191

Technical Paper / dx.doi.org/10.13182/NSE05-15

Calculations of Proton-Induced Neutron Production Cross Sections on 232Th up to 1.6 GeV

B. Sarer, M. Günay, A. Aydin, E. Tel, A. Arasoglu

Nuclear Science and Engineering / Volume 153 / Number 2 / June 2006 / Pages 192-199

Technical Note / dx.doi.org/10.13182/NSE06-A2605

Number 3

Electronic Structure of High Oxidation State Actinide Species: Theoretical and Experimental Approaches

Sandrine Hilaire, Dominique Guillaumont, Fabien Gutierez, Christophe Denauwer, Franck Wastin, Eric Colineau, Thomas Gouder, Jean Rebizant, Jean-Claude Berthet, Daniel Meyer, Eric Simoni

Nuclear Science and Engineering / Volume 153 / Number 3 / July 2006 / Pages 203-206

Technical Paper / dx.doi.org/10.13182/NSE06-A2606

Modeling Selectivity in Liquid/Liquid Extraction

D. Guillaumont, Ph. Guilbaud, C. Sorel, F. Gutierrez, S. Chalmet, M. Defranceschi

Nuclear Science and Engineering / Volume 153 / Number 3 / July 2006 / Pages 207-222

Technical Paper / dx.doi.org/10.13182/NSE06-A2607

Complexation of Lanthanide(III) and Actinide(III) Cations with Tridentate Nitrogen-Donor Ligands: A Luminescence and Spectrophotometric Study

M. Miguirditchian, D. Guillaneux, N. François, S. Airvault, S. Ducros, D. Thauvin, C. Madic, M. Illemassène, G. Lagarde, J.-C. Krupa

Nuclear Science and Engineering / Volume 153 / Number 3 / July 2006 / Pages 223-232

Technical Paper / dx.doi.org/10.13182/NSE06-A2608

FUJI: A Comparative Irradiation Test with Pellet, Sphere-Pac, and Vipac Fuels

Ch. Hellwig, K. Bakker, T. Ozawa, M. Nakamura, F. Ingold, L. Å. Nordström, Y. Kihara

Nuclear Science and Engineering / Volume 153 / Number 3 / July 2006 / Pages 233-244

Technical Paper / dx.doi.org/10.13182/NSE06-A2609

Oxide and Nitride TRU Fuels: Lessons Drawn from the CONFIRM and FUTURE Projects of the 5th European Framework Program

Sylvie Pillon, J. Wallenius

Nuclear Science and Engineering / Volume 153 / Number 3 / July 2006 / Pages 245-252

Technical Paper / dx.doi.org/10.13182/NSE06-A2610

Promising Pyrochemical Actinide/Lanthanide Separation Processes Using Aluminum

Olivier Conocar, Nicolas Douyere, Jean-Paul Glatz, Jérôme Lacquement, Rikard Malmbeck, Jérôme Serp

Nuclear Science and Engineering / Volume 153 / Number 3 / July 2006 / Pages 253-261

Technical Paper / dx.doi.org/10.13182/NSE06-A2611

Zirconolite for Minor Actinide Containment and Alpha Irradiation Resistance

F. Jorion, X. Deschanels, T. Advocat, F. Desmouliere, J. N. Cachia, S. Peuget, D. Roudil, G. Leturcq

Nuclear Science and Engineering / Volume 153 / Number 3 / July 2006 / Pages 262-271

Technical Paper / dx.doi.org/10.13182/NSE06-A2612

Development and Characterization of Rare Earth-Rich Glassy Matrices Envisaged for the Immobilization of Concentrated Nuclear Waste Solutions

I. Bardez, D. Caurant, J. L. Dussossoy, P. Loiseau, C. Gervais, F. Ribot, D. R. Neuville, N. Baffier, C. Fillet

Nuclear Science and Engineering / Volume 153 / Number 3 / July 2006 / Pages 272-284

Technical Paper / dx.doi.org/10.13182/NSE06-A2613

Contribution of Monte Carlo Modeling to Understanding the Alteration of Nuclear Glasses by Water

Aurélien Ledieu, François Devreux, Philippe Barboux, Yves Minet

Nuclear Science and Engineering / Volume 153 / Number 3 / July 2006 / Pages 285-300

Technical Paper / dx.doi.org/10.13182/NSE06-A2614

 
Questions or comments about the site? Contact the ANS Webmaster.
advertisement