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Volume 60

Number 2

  • Table of Contents
  • Melt-III(A. E. Waltar, W. L. Partain, D. C. Kolesar, L. D. O'Dell, A. Padilla, Jr., J. C. Sonnichsen, N. P. Wilburn, H. J. Willenberg)

Numerical Solution of the Transport Equation by Collocation with Bivariate Splines

L. Finkelstein, A. Krumbein

Nuclear Science and Engineering / Volume 60 / Number 2 / June 1976 / Pages 113-119

Technical Paper / dx.doi.org/10.13182/NSE76-A26867

Finite Element Solutions of Space-Time Nonlinear Reactor Dynamics

Dong H. Nguyen, David Salinas

Nuclear Science and Engineering / Volume 60 / Number 2 / June 1976 / Pages 120-130

Technical Paper / dx.doi.org/10.13182/NSE76-A26868

Prediction of Statistical Error in Monte Carlo Transport Calculations

Harvey J. Amster, M. Jahed Djomehri

Nuclear Science and Engineering / Volume 60 / Number 2 / June 1976 / Pages 131-142

Technical Paper / dx.doi.org/10.13182/NSE76-A26869

Criticality of Plutonium-Uranium Nitrate Solutions

R. C. Lloyd, E. D. Clayton

Nuclear Science and Engineering / Volume 60 / Number 2 / June 1976 / Pages 143-146

Technical Paper / dx.doi.org/10.13182/NSE76-A26870

A Pulsed Activation Measurement of the Doppler Effect of Uranium-238 over the Temperature Range 300 to 3115 K

S. K. Bhattacharyya, G. J. Russell, W. K. Foell

Nuclear Science and Engineering / Volume 60 / Number 2 / June 1976 / Pages 147-168

Technical Paper / dx.doi.org/10.13182/NSE76-A26871

Experimental and Theoretical Investigations of Tritium Production in a Controlled Thermonuclear Reactor Blanket Model

R. Herzing, L. Kuypers, P. Cloth, D. Filges, R. Hecker, N. Kirch

Nuclear Science and Engineering / Volume 60 / Number 2 / June 1976 / Pages 169-175

Technical Paper / dx.doi.org/10.13182/NSE76-A26872

Sodium-Water-Reaction Test and Evaluation for a Protected Bayonet-Tube Steam Generator

S. M. Cho, E. C. Govignon, G. J. Degutis

Nuclear Science and Engineering / Volume 60 / Number 2 / June 1976 / Pages 176-186

Technical Paper / dx.doi.org/10.13182/NSE76-A26873

Measurement of Cross Sections for the 59Co(n,p)59Fe Reaction Near Threshold

Donald L. Smith, James W. Meadows

Nuclear Science and Engineering / Volume 60 / Number 2 / June 1976 / Pages 187-188

Technical Note / dx.doi.org/10.13182/NSE76-A26874

On-Line Prediction of the Power Distribution Within Boiling Water Reactors

Yasuo Nishizawa, Takashi Kiguchi, Hiroshi Motoda

Nuclear Science and Engineering / Volume 60 / Number 2 / June 1976 / Pages 189-192

Technical Note / dx.doi.org/10.13182/NSE76-A26875