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Home / Publications / Journals / Nuclear Science and Engineering / Volume 110 / Number 2

Volume 110

Number 2

Table of Contents
SNCONV(K. Ganguly, G. Tucker, E. J. Allen, H. D. Victory, Jr.)
Comment on “Time-Independent Neutronic Analysis of the Chernobyl Accident”(Frej Wasastjerna)
Reply to “Comment on ‘Time-Independent Neutronir Analysis of the Chernobyl Accident’”(P. A. Landeyro)

Electrical Conductivity of UF₄-K/KF Gas Partially Ionized by Fission Fragments

Yoichi Watanabe, Jacob Appelbaum, Isaac Maya

Nuclear Science and Engineering / Volume 110 / Number 2 / February 1992 / Pages 109-127

Technical Papers / dx.doi.org/10.13182/NSE92-A23881

Study of Actinide Photonuclear Reactions Induced by Gamma Radiation from Neutron Capture

L. P. Geraldo, M. T. F. Cesar, M. A. P. V. Moraes

Nuclear Science and Engineering / Volume 110 / Number 2 / February 1992 / Pages 128-133

Technical Papers / dx.doi.org/10.13182/NSE92-A23882

Gamma-Ray and Neutron Dose-Equivalent Buildup Factors for Infinite Slabs

W. L. Dunn, A. M. Yacout, F. O′Foghludha

Nuclear Science and Engineering / Volume 110 / Number 2 / February 1992 / Pages 134-156

Technical Papers / dx.doi.org/10.13182/NSE92-A23883

New Approximate Orientation Averaging of the Water Molecule Interacting with the Thermal Neutron

Mihailo I. Marković, Djordje M. Minć, Aleksandar D. Rakić

Nuclear Science and Engineering / Volume 110 / Number 2 / February 1992 / Pages 157-164

Technical Papers / dx.doi.org/10.13182/NSE92-A23884

Suitability of ⁷⁹Kr as a Reactor-Based Source of Slow Positrons

A. P. Mills, Jr.

Nuclear Science and Engineering / Volume 110 / Number 2 / February 1992 / Pages 165-167

Technical Papers / dx.doi.org/10.13182/NSE92-A23885

Neutron Spectra and Flux Calculation in Thermalizing Regions in Liquid-Metal Reactors

Nasir M. Mirza, K. O. Ott

Nuclear Science and Engineering / Volume 110 / Number 2 / February 1992 / Pages 168-176

Technical Notes / dx.doi.org/10.13182/NSE92-A23886

Analysis of Overall Temperature Coefficient of Reactivity of the VHTRC-1 Core with a Nuclear Design Code System for the High-Temperature Engineering Test Reactor

Kiyonobu Yamashita, Isao Murata, Ryuichi Shindo

Nuclear Science and Engineering / Volume 110 / Number 2 / February 1992 / Pages 177-185

Technical Notes / dx.doi.org/10.13182/NSE92-A23887

Fuel Assembly Assay by Neutron Interrogation in a Lead Slowing-Down-Time Spectrometer

Ernesto C. Vanterpool, Rudolf E. Slovacek, Donald R. Harris, Robert C. Block

Nuclear Science and Engineering / Volume 110 / Number 2 / February 1992 / Pages 186-194

Technical Notes / dx.doi.org/10.13182/NSE92-A23888

The Neutron Streaming Term in a Generalized Coordinate System

Yuan-Shun Way, Yann-Ming Way

Nuclear Science and Engineering / Volume 110 / Number 2 / February 1992 / Pages 195-199

Technical Notes / dx.doi.org/10.13182/NSE92-A23889

Dynamics of Continuously Fueled Homogeneous Fission Reactors

P. J. Roberts, A. A. Harms

Nuclear Science and Engineering / Volume 110 / Number 2 / February 1992 / Pages 200-204

Technical Notes / dx.doi.org/10.13182/NSE92-A23890

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