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Volume 135

Number 1 | Number 2 | Number 3

Number 1

Analysis of Differences in Void Coefficient Predictions for Mixed-Oxide-Fueled Tight-Pitch Light Water Reactor Cells

Hironobu Unesaki, Seiji Shiroya, Keiji Kanda, Stéphane Cathalau, Franck-Olivier Carré, Otohiko Aizawa, Toshikazu Takeda

Nuclear Science and Engineering / Volume 135 / Number 1 / May 2000 / Pages 1-22

Technical Paper

Measurement of Activation Reaction Rate Distributions in a Lead Assembly Bombarded with 500-MeV Protons

Hiroshi Takada, Shin-ichro Meigo, Toshinobu Sasa, Kazufumi Tsujimoto, Hideshi Yasuda

Nuclear Science and Engineering / Volume 135 / Number 1 / May 2000 / Pages 23-32

Technical Paper

Epithermal Inverse Kinetic Measurements and Their Interpretation Using a Two-Group Point-Kinetic Model

Marc Rosselet, Rakesh Chawla, Tony Williams

Nuclear Science and Engineering / Volume 135 / Number 1 / May 2000 / Pages 33-47

Technical Paper

Influence of the Thermal Cutoff Energy on the Calculation of Neutronic Parameters for Light Water Reactor Lattices

Jean-Marie Paratte, Sandro Pelloni

Nuclear Science and Engineering / Volume 135 / Number 1 / May 2000 / Pages 48-56

Technical Paper

Properties of a Cold-Neutron Irradiation Facility for In Vitro Research on Boron Neutron Capture Therapy at the Geesthacht Neutron Facility

L. Lüdemann, R. Kampmann, W. Sosaat, P. Staron, P. Wille

Nuclear Science and Engineering / Volume 135 / Number 1 / May 2000 / Pages 57-63

Technical Paper

Verification of the Neutron Flux of a Modified Zero-Power Reactor Using a Neutron Activation Method

Lung Kwang Pan, Cheng Si Tsao

Nuclear Science and Engineering / Volume 135 / Number 1 / May 2000 / Pages 64-72

Technical Paper

A Multigroup Albedo Method for Transport Calculations: Application to the Orphée Core

S. Rauck, R. Sanchez, I. Zmijarevic, M. Nobile

Nuclear Science and Engineering / Volume 135 / Number 1 / May 2000 / Pages 73-83

Technical Paper

Nuclide Importance and the Steady-State Burnup Equation

Hiroshi Sekimoto, Atsushi Nemoto

Nuclear Science and Engineering / Volume 135 / Number 1 / May 2000 / Pages 84-102

Technical Paper

Number 2

Differential Sampling Applied to Mammography Image Simulation

Douglas E. Peplow, Kuruvilla Verghese

Nuclear Science and Engineering / Volume 135 / Number 2 / June 2000 / Pages 103-122

Technical Paper

Neutron Transport in Spatially Random Media: An Assessment of the Accuracy of First Order Smoothing

M. M. R. Williams

Nuclear Science and Engineering / Volume 135 / Number 2 / June 2000 / Pages 123-140

Technical Paper

New High-Resolution Fission Cross-Section Measurements of 233U in the 0.4-eV to 700-keV Energy Range

K. H. Guber, R. R. Spencer, L. C. Leal, J. A. Harvey, N. W. Hill, G. Dos Santos, R. O. Sayer, D. C. Larson

Nuclear Science and Engineering / Volume 135 / Number 2 / June 2000 / Pages 141-149

Technical Paper

Reactivity Control Method for Direct Use of Spent Pressurized Water Reactor Fuel in CANDU Reactors (DUPIC)

Hangbok Choi, Won Il Ko, Myung Seung Yang

Nuclear Science and Engineering / Volume 135 / Number 2 / June 2000 / Pages 150-164

Technical Paper

SPACON - A Theoretical Model for Calculating the Heat Transport Properties in Sphere-Pac Fuel Pins

F. Botta, C. Hellwig

Nuclear Science and Engineering / Volume 135 / Number 2 / June 2000 / Pages 165-176

Technical Paper

Experimental Study of Two-Phase Flow Oscillation in Natural Circulation

S. Y. Jiang, X. X. Wu, Y. J. Zhang

Nuclear Science and Engineering / Volume 135 / Number 2 / June 2000 / Pages 177-189

Technical Paper

On the Curvature of Transmitted Intensity Plots in Broad Beam Studies

A. H. El-Kateb

Nuclear Science and Engineering / Volume 135 / Number 2 / June 2000 / Pages 190-198

Technical Paper

Number 3

Spatial and Angular Moment Analysis of Continuous and Discretized Transport Problems

Patrick S. Brantley, Edward W. Larsen

Nuclear Science and Engineering / Volume 135 / Number 3 / July 2000 / Pages 199-226

Technical Paper

Measurement of Absolute Fission Yields in the Fast Neutron-Induced Fission of Actinides: 238U, 237Np, 238Pu, 240Pu, 243Am, and 244Cm by Track-Etch-cum-Gamma Spectrometry

R. H. Iyer, H. Naik, A. K. Pandey, P. C. Kalsi, R. J. Singh, A. Ramaswami, A. G. C. Nair

Nuclear Science and Engineering / Volume 135 / Number 3 / July 2000 / Pages 227-245

Technical Paper

Effects of Differing Energy Dependences in Three Level-Density Models on Calculated Cross Sections

C. Y. Fu

Nuclear Science and Engineering / Volume 135 / Number 3 / July 2000 / Pages 246-259

Technical Paper

16O(n,p)16N Reaction Cross Sections Around 14 MeV

M.Subasi, E. Gültekin, I. A. Reyhancan, Y. Özbir, G. Tarcan, M. Sirin, M. N. Erduran

Nuclear Science and Engineering / Volume 135 / Number 3 / July 2000 / Pages 260-266

Technical Paper

Numerical Simulation of the Emergency Condenser of the SWR-1000

Eckhard Krepper, Andreas Schaffrath, Attila Aszódi

Nuclear Science and Engineering / Volume 135 / Number 3 / July 2000 / Pages 267-279

Technical Paper

Use of Axially Graded Burnable Boron for Hot-Spot Temperature Reduction in a Pressurized Water Reactor Core

M. Segev, A. Galperin, E. Schwageraus

Nuclear Science and Engineering / Volume 135 / Number 3 / July 2000 / Pages 280-287

Technical Paper

Lognormal Size Distribution Theory for Deposition of Polydisperse Aerosol Particles

S. H. Park, K. W. Lee

Nuclear Science and Engineering / Volume 135 / Number 3 / July 2000 / Pages 288-295

Technical Note

Application of a Simple Ramsauer Model for Neutron Total Cross Sections for Nuclear Mass Numbers A < 40

S. M. Grimes, J. D. Anderson, R. W. Bauer

Nuclear Science and Engineering / Volume 135 / Number 3 / July 2000 / Pages 296-303

Technical Note

Calculation of the Dancoff Factor for Pebble Bed Reactors

J. Valko, P. V. Tsvetkov, J. E. Hoogenboom

Nuclear Science and Engineering / Volume 135 / Number 3 / July 2000 / Pages 304-307

Technical Note

 
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