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Volume 74

Number 2

Table of Contents
Eigenvalues of the Neutron Transport Equation with Anisotropic Scattering(N. G. Sjöstrand)
Reply to a Comment on “Eigenvalues of the Neutron Transport Equation with Anisotropic Scattering”(Trine-Yie Dawn)
Nuclear Power Plant Engineering(Ronald J. Onega)
On the Correct Use of the Bayesian Method for Reactor Core Melt Frequency(Harry F. Martz, Jr.)

Characteristics and Stability Analyses for Two-Phase Flow Equation Systems with Viscous Terms

Masahiko Arai

Nuclear Science and Engineering / Volume 74 / Number 2 / May 1980 / Pages 77-83

Technical Paper / dx.doi.org/10.13182/NSE80-A19624

A Symbiotic Water Breeder Reactor System

Yigal Ronen, Samuel Carmona

Nuclear Science and Engineering / Volume 74 / Number 2 / May 1980 / Pages 84-94

Technical Paper / dx.doi.org/10.13182/NSE80-A19625

Measurements of Moderator Temperature Coefficients of Reactivity for Pressure-Tube-Type Reactors

T. Otsuka, N. Fukumura, Y. Hachiya

Nuclear Science and Engineering / Volume 74 / Number 2 / May 1980 / Pages 95-105

Technical Paper / dx.doi.org/10.13182/NSE80-A19626

Fission-Product Energy Release for Times Following Thermal-Neutron Fission of ²³⁵U Between 2 and 14 000 s

J. K. Dickens, T. A. Love, J. W. McConnell, R. W. Peelle

Nuclear Science and Engineering / Volume 74 / Number 2 / May 1980 / Pages 106-129

Technical Paper / dx.doi.org/10.13182/NSE80-A19627

A Separation Method for the Transport Equation and Sensitivity Theory for Fusion-Fission Hybrid Analysis

M. Z. Youssef, R. W. Conn

Nuclear Science and Engineering / Volume 74 / Number 2 / May 1980 / Pages 130-139

Technical Paper / dx.doi.org/10.13182/NSE80-A19628

Temperature Effects on Charged-Particle-Induced Cross Sections

Dermott E. Cullen, Robert J. Howerton, Ernest F. Plechaty

Nuclear Science and Engineering / Volume 74 / Number 2 / May 1980 / Pages 140-147

Technical Note / dx.doi.org/10.13182/NSE80-A19629

Application of Generalized Variational Principles to Controlled Thermonuclear Reactor Neutronics Analysis

E. T. Cheng

Nuclear Science and Engineering / Volume 74 / Number 2 / May 1980 / Pages 147-153

Technical Note / dx.doi.org/10.13182/NSE80-A19630

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