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Volume 161

Number 1 | Number 2 | Number 3

Number 1

Recycling-Independent Core Design for the ENHS Fuel Self-Sustaining Reactor

Lanfranco Monti, Ki-Bog Lee, Massimiliano Fratoni, Marco Sumini, Ehud Greenspan

Nuclear Science and Engineering / Volume 161 / Number 1 / January 2009 / Pages 1-21

Technical Paper / dx.doi.org/10.13182/NSE162-01

Application of hp Adaptivity to the Multigroup Diffusion Equations

Yaqi Wang, Jean Ragusa

Nuclear Science and Engineering / Volume 161 / Number 1 / January 2009 / Pages 22-48

Technical Paper / dx.doi.org/10.13182/NSE161-22

An Analytical Approximation Solution for a Time-Dependent Neutron Transport Problem with External Source and Delayed Neutron Production

B. Merk

Nuclear Science and Engineering / Volume 161 / Number 1 / January 2009 / Pages 49-67

Technical Paper / dx.doi.org/10.13182/NSE161-49

Reducing Parasitic Thermal Neutron Absorption in Graphite Reactors by 30%

C. D. Bowman, E. G. Bilpuch, D. C. Bowman, A. S. Crowell, C. R. Howell, K. McCabe, G. A. Smith, A. P. Tonchev, W. Tornow, V. Violet, R. B. Vogelaar, R. L. Walter, J. Yingling

Nuclear Science and Engineering / Volume 161 / Number 1 / January 2009 / Pages 68-77

Technical Paper / dx.doi.org/10.13182/NSE161-68

Possible Configurations for the Thorium Molten Salt Reactor and Advantages of the Fast Nonmoderated Version

L. Mathieu, D. Heuer, E. Merle-Lucotte, R. Brissot, C. Le Brun, E. Liatard, J.-M. Loiseaux, O. MÃplan, A. Nuttin, D. Lecarpentier

Nuclear Science and Engineering / Volume 161 / Number 1 / January 2009 / Pages 78-89

Technical Paper / dx.doi.org/10.13182/NSE07-49

Calculation and Evaluations for n + 54,56,57,58,natFe Reactions

Yinlu Han, Yue Zhang, Hairui Guo

Nuclear Science and Engineering / Volume 161 / Number 1 / January 2009 / Pages 90-110

Technical Paper / dx.doi.org/10.13182/NSE161-90

The Fast Fission Factor Revisited

Lénárd Pál, Imre Pázsit

Nuclear Science and Engineering / Volume 161 / Number 1 / January 2009 / Pages 111-118

Technical Paper / dx.doi.org/10.13182/NSE161-111

Neutrons from a Proton-Driven Deuterium Target as a Possible Competitor to Spallation for Nuclear Energy Applications

C. D. Bowman, D. C. Bowman, E. G. Bilpuch, A. S. Crowell, C. R. Howell, K. McCabe, G. A. Smith, A. P. Tonchev, W. Tornow, V. Vylet, R. L. Walter

Nuclear Science and Engineering / Volume 161 / Number 1 / January 2009 / Pages 119-124

Technical Note / dx.doi.org/10.13182/NSE161-119

External Neutron Drive for Subcritical Reactors

D. C. Bowman, C. D. Bowman

Nuclear Science and Engineering / Volume 161 / Number 1 / January 2009 / Pages 125-129

Technical Note / dx.doi.org/10.13182/NSE161-125

Number 2

R-Matrix Analysis of 238U High-Resolution Neutron Transmissions and Capture Cross Sections in the Energy Range 0 to 20 keV

H. Derrien, A. Courcelle, L. C. Leal, N. M. Larson

Nuclear Science and Engineering / Volume 161 / Number 2 / February 2009 / Pages 131-159

Technical Paper / dx.doi.org/10.13182/NSE161-131

Review of the CRAC and SILENE Criticality Accident Studies

Francis Barbry, Patrick Fouillaud, Pascal Grivot, Ludovic Reverdy

Nuclear Science and Engineering / Volume 161 / Number 2 / February 2009 / Pages 160-187

Technical Paper / dx.doi.org/10.13182/NSE08-15

Fission Product Experimental Program: Validation and Computational Analysis

Nicolas Leclaire, Tatiana Ivanova, Eric Latang, Emmanuel Girault, Jean-François Thro

Nuclear Science and Engineering / Volume 161 / Number 2 / February 2009 / Pages 188-215

Technical Paper / dx.doi.org/10.13182/NSE07-86

Coupled Space-Angle Adaptivity for Radiation Transport Calculations

HyeongKae Park, Cassiano R. E. de Oliveira

Nuclear Science and Engineering / Volume 161 / Number 2 / February 2009 / Pages 216-234

Technical Paper / dx.doi.org/10.13182/NSE161-216

The Impact of Core Flow Rate on the Hydrogen Water Chemistry Efficiency in Boiling Water Reactors

Tsung-Kuang Yeh, Mei-Ya Wang

Nuclear Science and Engineering / Volume 161 / Number 2 / February 2009 / Pages 235-244

Technical Paper / dx.doi.org/10.13182/NSE161-235

Shape Optimization of 19-Pin Wire-Wrapped Fuel Assembly of LMR Using Multiobjective Evolutionary Algorithm

Wasim Raza, Kwang-Yong Kim

Nuclear Science and Engineering / Volume 161 / Number 2 / February 2009 / Pages 245-254

Technical Note / dx.doi.org/10.13182/NSE161-245

Number 3

New Numerical Solution with the Method of Short Characteristics for 2-D Heterogeneous Cartesian Cells in the APOLLO2 Code: Numerical Analysis and Tests

Emiliano Masiello, Richard Sanchez, Igor Zmijarevic

Nuclear Science and Engineering / Volume 161 / Number 3 / March 2009 / Pages 257-278

Technical Paper / dx.doi.org/10.13182/NSE161-257

A New Paradigm for Local-Global Coupling in Whole-Core Neutron Transport

E. E. Lewis, M. A. Smith, G. Palmiotti

Nuclear Science and Engineering / Volume 161 / Number 3 / March 2009 / Pages 279-288

Technical Paper / dx.doi.org/10.13182/NSE161-279

Effect of 24195Am(n,) Reaction Branching Ratio on Fuel Cycle and Reactor Design Characteristics

Leonid Golyand, Eugene Shwageraus, Yigal Ronen

Nuclear Science and Engineering / Volume 161 / Number 3 / March 2009 / Pages 289-302

Technical Paper / dx.doi.org/10.13182/NSE161-289

Hafnium Resonance Parameter Analysis Using Neutron Capture and Transmission Experiments

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

Nuclear Science and Engineering / Volume 161 / Number 3 / March 2009 / Pages 303-320

Technical Paper / dx.doi.org/10.13182/NSE161-303

Beryllium and Graphite High-Accuracy Total Cross-Section Measurements in the Energy Range from 24 to 900 keV

Y. Danon, R. C. Block, M. J. Rapp, F. J. Saglime, G. Leinweber, D. P. Barry, N. J. Drindak, J. G. Hoole

Nuclear Science and Engineering / Volume 161 / Number 3 / March 2009 / Pages 321-330

Technical Paper / dx.doi.org/10.13182/NSE161-321

Theoretical Calculations and Analysis for the n + 59Co Reaction up to 20 MeV

Yue Zhang, Hairui Guo, Yinlu Han, Qingbiao Shen

Nuclear Science and Engineering / Volume 161 / Number 3 / March 2009 / Pages 331-345

Technical Paper / dx.doi.org/10.13182/NSE161-331

Scaling Relations for Intermediate-Energy Proton-Nucleus Reactions with Small Energy Losses

R. J. Peterson

Nuclear Science and Engineering / Volume 161 / Number 3 / March 2009 / Pages 346-356

Technical Paper / dx.doi.org/10.13182/NSE161-346

Subcritical Measurements of a Plutonium Sphere Reflected by Polyethylene and Acrylic

Jesson Hutchinson, Timothy Valentine

Nuclear Science and Engineering / Volume 161 / Number 3 / March 2009 / Pages 357-362

Technical Paper / dx.doi.org/10.13182/NSE161-357

A Monte Carlo Approach to Nuclear Model Parameter Uncertainties Propagation

Cyrille De Saint Jean, Gilles Noguere, Benoit Habert, Bertrand Iooss

Nuclear Science and Engineering / Volume 161 / Number 3 / March 2009 / Pages 363-370

Technical Paper / dx.doi.org/10.13182/NSE161-363

 
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