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Volume 113

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Nuclear Science and Engineering / Volume 113 / Number 4

April 1993

Thermohydraulic Behavior of the Liquid-Metal Natural-Circulation Target of the Spallation Neutron Source at Paul Scherrer Institute

Y. Takeda, W. E. Fischer

Nuclear Science and Engineering / Volume 113 / Number 4 / Pages 287-299

April 1993

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Suppression of Vapor Explosions by Dilute Aqueous Polymer Solutions

M. F. Dowling, B. M. Ip, S. I. Abdel-Khalik

Nuclear Science and Engineering / Volume 113 / Number 4 / Pages 300-313

April 1993

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Creating and Using a Type of Free-Form Geometry in Monte Carlo Particle Transport

Daniel E. Wessol, Floyd J. Wheeler

Nuclear Science and Engineering / Volume 113 / Number 4 / Pages 314-323

April 1993

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Quantifying the Reliability of Uncertainty Predictions in Monte Carlo Fast Reactor Physics Calculations

L. L. Carter, T. L. Miles, S. E. Binney

Nuclear Science and Engineering / Volume 113 / Number 4 / Pages 324-338

April 1993

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A New Approach and Computational Algorithm for Sensitivity/Uncertainty Analysis for SED and SAD with Application to Beryllium Integral Experiments

Peter M. Song, Mahmoud Z. Youssef, Mohamed A. Abdou

Nuclear Science and Engineering / Volume 113 / Number 4 / Pages 339-366

April 1993

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Table of Contents

Nuclear Science and Engineering / Volume 113 / Number 1

January 1993

Laboratory Measurement of the Heat Capacity of Urania up to 8000 K: I. Experiment

C. Ronchi, J. P. Hiernaut, R. Selfslag, G. J. Hyland

Nuclear Science and Engineering / Volume 113 / Number 1 / Pages 1-19

January 1993

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Heavy Nucleus Resonant Absorption Calculation Benchmarks

H. Tellier, M. Coste, C. Raepsaet, C. Van der Gucht

Nuclear Science and Engineering / Volume 113 / Number 1 / Pages 20-30

January 1993

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Langevin Equation Approach to Reactor Noise Analysis: Stochastic Transport Equation

A. Ziya Akcasu, Alison M. Stolle

Nuclear Science and Engineering / Volume 113 / Number 1 / Pages 31-55

January 1993

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A Stochastic Cellular Automata Model for Neutron Transport

Michael J. Gaeta, Bahram Nassersharif

Nuclear Science and Engineering / Volume 113 / Number 1 / Pages 56-69

January 1993

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Pressurized Water Reactor Core Parameter Prediction Using an Artificial Neural Network

Han Gon Kim, Soon Heung Chang, Byung Ho Lee

Nuclear Science and Engineering / Volume 113 / Number 1 / Pages 70-76

January 1993

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A Test of MCNP with a 6Li-Glass Moderating Neutron Detector

J. C. Wang, Gary L. Jensen, J. B. Czirr

Nuclear Science and Engineering / Volume 113 / Number 1 / Pages 77-85

January 1993

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Multigroup Antiproton Transport and Fission

B. R. Wienke, R. E. Seamon, D. G. Madland

Nuclear Science and Engineering / Volume 113 / Number 1 / Pages 86-92

January 1993

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On “Simultaneous Estimation of Neutron Density and Reactivity in a Nuclear Reactor Using a Bank of Kalman Filters”

Attila Rácz

Nuclear Science and Engineering / Volume 113 / Number 1 / Pages 93-95

January 1993

Reply to “On ‘Simultaneous Estimation of Neutron Density and Reactivity in a Nuclear Reactor Using a Bank of Kalman Filters’ ”

Carlos E. D’Attellis

Nuclear Science and Engineering / Volume 113 / Number 1 / Page 95

January 1993

Table of Contents

Nuclear Science and Engineering / Volume 113 / Number 2

February 1993

Neutronic Decoupling and Space-Dependent Nuclear Characteristics for Large Liquid-Metal Fast Breeder Reactor Cores

Toshio Sanda, Fumiaki Nakashima, Keisho Shirakata

Nuclear Science and Engineering / Volume 113 / Number 2 / Pages 97-108

February 1993

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Study of Compact Fast Reactor Core Designs

Tehsin Hamid, K. O. Ott

Nuclear Science and Engineering / Volume 113 / Number 2 / Pages 109-121

February 1993

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