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Volume 91

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Nuclear Science and Engineering / Volume 91 / Number 1

September 1985

Burnup Sensitivity Analysis in a Fast Breeder Reactor—Part I: Sensitivity Calculation Method with Generalized Perturbation Theory

T. Takeda, T. Umano

Nuclear Science and Engineering / Volume 91 / Number 1 / Pages 1-10

September 1985

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Burnup Sensitivity Analysis in a Fast Breeder Reactor—Part II: Prediction Accuracy of Burnup Characteristics

Takanobu Kamei, Tadashi Yoshida, Toshikazu Takeda, Takuya Umano

Nuclear Science and Engineering / Volume 91 / Number 1 / Pages 11-33

September 1985

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Application of the Hermite Method for Finite Element Reactor Calculations

A. Hébert

Nuclear Science and Engineering / Volume 91 / Number 1 / Pages 34-58

September 1985

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On the Markov Chain Analysis of Source Iteration Monte Carlo Procedures for Criticality Problems: I

T. Elperin, A. Dubi

Nuclear Science and Engineering / Volume 91 / Number 1 / Pages 59-76

September 1985

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On the Markov Chain Analysis of Source Iteration Monte Carlo Procedures for Criticality Problems: II

A. Dubi, T. Elperin

Nuclear Science and Engineering / Volume 91 / Number 1 / Pages 77-83

September 1985

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Transport of Thermal Neutrons in Crystalline and Amorphous Polyethylene at Various Temperatures

K. Swaminathan, S. P. Tewari

Nuclear Science and Engineering / Volume 91 / Number 1 / Pages 84-94

September 1985

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Thermal Neutron Scattering Kernel for Polyethylene of Various Degrees of Crystallinity

K. Swaminathan, S. P. Tewari

Nuclear Science and Engineering / Volume 91 / Number 1 / Pages 95-108

September 1985

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Effect of Overlying Liquid Layer on Dryout Heat Flux Measurements

J. S. Marshall, V. K. Dhir

Nuclear Science and Engineering / Volume 91 / Number 1 / Pages 109-113

September 1985

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Prompt Neutron Emission Probabilities Following Spontaneous and Thermal Neutron Fission

J. W. Boldeman, M. G. Hines

Nuclear Science and Engineering / Volume 91 / Number 1 / Pages 114-116

September 1985

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Excitation of Neutron Flux Waves in Reactor Core Transients

J. F. Carew, P. Neogy

Nuclear Science and Engineering / Volume 91 / Number 1 / Pages 117-122

September 1985

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Table of Contents

Nuclear Science and Engineering / Volume 91 / Number 3

November 1985

Measurement of Flow in a Horizontal Pipe Using the Pulsed Photon Activation Technique

Thomas F. Lin, Robert C. Block, Owen C. Jones, Jr., Richard T. Lahey, Jr., Michio Murase

Nuclear Science and Engineering / Volume 91 / Number 3 / Pages 235-247

November 1985

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Survey of Natural-Circulation Cooling in U.S. Pressurized Water Reactors

Brent E. Boyack

Nuclear Science and Engineering / Volume 91 / Number 3 / Pages 248-261

November 1985

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Probabilistic Evaluation of Channel Coolant Flow Rates with Flow Correlation Among Fuel Channels in the FUGEN Reactor

Katsuhiro Sakai, Satoru Sugawara, Hisashi Hishida, Tetsuo Kobori

Nuclear Science and Engineering / Volume 91 / Number 3 / Pages 262-278

November 1985

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Application of Neutron Transport Green's Functions to the Calculation of Pressure Vessel Fluence

J. F. Carew, A. L. Aronson, D. M. Cokinos, A. Prince, M. Todosow

Nuclear Science and Engineering / Volume 91 / Number 3 / Pages 279-285

November 1985

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The Nonlinear Dynamics of the Oklo Natural Reactor

Z. Bilanovic, A. A. Harms

Nuclear Science and Engineering / Volume 91 / Number 3 / Pages 286-292

November 1985

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Improvements in Calculating Neutron Transmission Probabilities in Unit-Cell Interface-Current Codes

B. A. Worley

Nuclear Science and Engineering / Volume 91 / Number 3 / Pages 293-304

November 1985

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Delayed-Neutron Energy Spectra of 93-97Rb and 143-145Cs

R. C. Greenwood, A. J. Caffrey

Nuclear Science and Engineering / Volume 91 / Number 3 / Pages 305-323

November 1985

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Multigroup Legendre Coefficients for the Diamond Difference Continuous Slowing Down Operator

J. E. Morel

Nuclear Science and Engineering / Volume 91 / Number 3 / Pages 324-331

November 1985

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