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Volume 91

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Nuclear Science and Engineering / Volume 91 / Number 1

September 1985

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Nuclear Science and Engineering / Volume 91 / Number 3

November 1985

Table of Contents

Nuclear Science and Engineering / Volume 91 / Number 4

December 1985

Table of Contents

Nuclear Science and Engineering / Volume 91 / Number 2

October 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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On the Reconstruction of Local Homogeneous Neutron Flux and Current Distributions of Light Water Reactors from Nodal Schemes

K. Koebke, L. Hetzelt

Nuclear Science and Engineering / Volume 91 / Number 2 / Pages 123-131

October 1985

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Variational Nodal Methods for Neutron Transport

I. Dilber and E. E. Lewis

Nuclear Science and Engineering / Volume 91 / Number 2 / Pages 132-142

October 1985

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Analysis of the Amplification of Deuterium-Tritium Neutron Sources: Part 1-Theory

M. Segev

Nuclear Science and Engineering / Volume 91 / Number 2 / Pages 143-152

October 1985

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Analysis of the Amplification of Deuterium-Tritium Neutron Sources: Part 2-Application

M. Segev, S. Taczanowski

Nuclear Science and Engineering / Volume 91 / Number 2 / Pages 153-161

October 1985

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Determination of Excitation Function of Triton Emission Reaction on Aluminum from Threshold up to 30 MeV via Activation in Diverse Neutron Fields and Unfolding Code Calculations

R. Wölfle, S. Sudár, S. M. Qaim

Nuclear Science and Engineering / Volume 91 / Number 2 / Pages 162-172

October 1985

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Measurements of 6Li and 7Li Neutron-Induced Tritium Production Cross Sections at 15 MeV

Eugene Goldberg, Ronald L. Barber, Patrick E. Barry, Norman A. Bonner, James E. Fontanilla, Clyde M. Griffith, Robert C. Haighf David R. Nethaway, George B. Hudson

Nuclear Science and Engineering / Volume 91 / Number 2 / Pages 173-186

October 1985

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