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Volume 22

Number 3

Table of Contents
Errata
Errata
Confidence Limits for Monte Carlo Calculations(G. L. Burrows, D. B. MacMillan)
On the Inclusion of Boundary Terms in Time-Dependent Synthesis Techniques(Martin Becker)
On Cadmium-Ratio Measurements for U²³⁵ and U²³³ Fission by Fission-Product Gamma Counting(D. Klein)
Intermediate Resonance Absorption at Low Energies(Rubin Goldstein)
On Transfer Cross Sections Between Overlapping Thermal Groups(H. Hembd)
Diffusion Coefficient of Thermal Neutrons for a Maxwellian Gas(B. Marsico, V. G. Molinari, R. Scozzafava)
An Approximate Solution of the Two-Overlapping-Thermal-Group Diffusion Equations(R. J. Breen, J. B. Yasinsky)
Directory of Nuclear Reactors - Volume V, Research, Test and Experimental Reactors(U. M. Staebler)
Reactor Handbook(D. G. Hurst)
Biological Effects of Neutron and Proton Irradiations(Titus C. Evans)
Industrial Uses of Large Radiation Sources(George R. Dietz)
Massive Radiation Techniques(George R. Dietz)
CCA - 93(R. A. Blaine)
CCA - 104(R. A. Blaine)
CCA - 105(R. A. Blaine)

The Application of Dynamic Programing to Fuel Management Optimization

Ian Wall and Henri Fenech

Nuclear Science and Engineering / Volume 22 / Number 3 / July 1965 / Pages 285-297

Technical Paper / dx.doi.org/10.13182/NSE65-A20933

Heat Transfer and Pressure Drop for Cross Flow through Banks of Multistart Helical Tubes with Uniform Inclinations and Uniform Longitudinal Pitches

P. V. Gilli

Nuclear Science and Engineering / Volume 22 / Number 3 / July 1965 / Pages 298-314

Technical Paper / dx.doi.org/10.13182/NSE65-A20934

Neutron Penetration Factors Obtained by Using Adjoint Transport Calculations

G. E. Hansen and H. A. Sandmeier

Nuclear Science and Engineering / Volume 22 / Number 3 / July 1965 / Pages 315-320

Technical Paper / dx.doi.org/10.13182/NSE65-A20935

Neutron-Wave Propagation Using the P₁ Approximation

Glen A. Mortensen and Harold P. Smith, Jr.

Nuclear Science and Engineering / Volume 22 / Number 3 / July 1965 / Pages 321-327

Technical Paper / dx.doi.org/10.13182/NSE65-A20936

An Asymptotically Correct Approximation to the Multidimensional Transport Equation

G. C. Pomraning

Nuclear Science and Engineering / Volume 22 / Number 3 / July 1965 / Pages 328-338

Technical Paper / dx.doi.org/10.13182/NSE65-A20937

Reflection and Transmission by a Strongly Absorbing Slab

André Mackel

Nuclear Science and Engineering / Volume 22 / Number 3 / July 1965 / Pages 339-349

Technical Paper / dx.doi.org/10.13182/NSE65-A20938

Geologic, Hydrologic, and Safety Considerations in the Storage of Radioactive Wastes in a Vault Excavated in Crystalline Rock

J. F. Proctor, I. W. Marine

Nuclear Science and Engineering / Volume 22 / Number 3 / July 1965 / Pages 350-365

Technical Paper / dx.doi.org/10.13182/NSE65-A20939

Equilibrium Spectra and Diffusion Lengths of Neutrons in Semi-Infinite Moderator Block—Part I

P. S. Grover and L. S. Kothari

Nuclear Science and Engineering / Volume 22 / Number 3 / July 1965 / Pages 366-372

Technical Paper / dx.doi.org/10.13182/NSE65-A20940

Formation of Se^77m, Sr^87m, Cd^111m and Ba^137m by Reactor Spectrum Neutrons for Use in Activation Analysis

Henry H. Kramer and Werner H. Wahl

Nuclear Science and Engineering / Volume 22 / Number 3 / July 1965 / Pages 373-382

Technical Paper / dx.doi.org/10.13182/NSE65-A20941

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