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Volume 114

Number 2

A Burnup-Compensated Madland-Nix Prompt Fission Neutron Source Term for Multigroup Nuclear Reactor Shielding Calculations

T. J. van Rooyen, G. P. de Beer

Nuclear Science and Engineering / Volume 114 / Number 2 / June 1993 / Pages 87-101

Technical Paper / dx.doi.org/10.13182/NSE93-A24020

A Model for Fission Product Release from Liquid-Metal Pools: Development and Sensitivity Investigation

P. R. McClure, M. T. Leonard, A. Razani

Nuclear Science and Engineering / Volume 114 / Number 2 / June 1993 / Pages 102-111

Technical Paper / dx.doi.org/10.13182/NSE93-A24021

Neutron Spectrum Measurements of a Thorium Dioxide Assembly

Paul S. Feigenbaum, Martin Becker, Donald R. Harris Bimal K. Malaviya, Robert C. Block, S. A. Hayashi, S. Yamamoto

Nuclear Science and Engineering / Volume 114 / Number 2 / June 1993 / Pages 112-117

Technical Paper / dx.doi.org/10.13182/NSE93-A24022

Calculation of Recoil Ion Effective Track Lengths in Neutron-Radiation-Induced Nucleation

Mark J. Harper

Nuclear Science and Engineering / Volume 114 / Number 2 / June 1993 / Pages 118-123

Technical Paper / dx.doi.org/10.13182/NSE93-A24023

Calculation of Neutron Superinelastic Scattering in 178mHf

G. Reffo and M. H. MacGregor

Nuclear Science and Engineering / Volume 114 / Number 2 / June 1993 / Pages 124-134

Technical Paper / dx.doi.org/10.13182/NSE93-A24024

Condensation on Nonspherical Aerosol Particles: Numerical Solutions in the Continuum Regime

S. K. Loyalka, J. L. Griffin

Nuclear Science and Engineering / Volume 114 / Number 2 / June 1993 / Pages 135-140

Technical Paper / dx.doi.org/10.13182/NSE93-A24025

Sensor Fault Detection with the Single Sensor Parity Relation

T. M. Tsai , H. P. Chou

Nuclear Science and Engineering / Volume 114 / Number 2 / June 1993 / Pages 141-148

Technical Paper / dx.doi.org/10.13182/NSE93-A24026

Measurements and Calculations of Radionuclides Created by 181Ta(γ,xn yp) Reactions for Bremsstrahlung Photons Produced by 150-MeV Electrons

J. K. Dickens , M. A. Miller

Nuclear Science and Engineering / Volume 114 / Number 2 / June 1993 / Pages 149-159

Technical Note / dx.doi.org/10.13182/NSE93-A24027

Analysis of ONEDANT Code Package for the Calculation of the Doppler Coefficient of Reactivity

I. Soares, W. F. Miller, Jr., R. T. Perry

Nuclear Science and Engineering / Volume 114 / Number 2 / June 1993 / Pages 160-167

Technical Note / dx.doi.org/10.13182/NSE93-A24028

Derivation of Anisotropic Diffusion Coefficients in a Large Annular Cavity

Eiichi Suetomi, Hiroshi Sekimoto

Nuclear Science and Engineering / Volume 114 / Number 2 / June 1993 / Pages 168-175

Technical Note / dx.doi.org/10.13182/NSE93-A24029