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Volume 33

Number 1

Table of Contents
Authors(J. F. L. M. Brukx, G. P. R. Hansen, P. Voj, Sadao Uchikawa, J. L. Stakebake, H. N. Robinson, Wiktor Żyszkowski, Klaus W. Klein, E. G. Samsel, J. R. Berreth, Charles R. Brinkman, Vinod K. Sikka, Roy T. King, P. K. Madden, R. V. Hesketh, Dennis G. Perry, Margaret L. Simmons, James S. Gilmore, E. D. Clayton, B. M. Durst, D. R. Duncan, M. M. Paxton)

Combined Free and Forced Convection Effects on Transient Temperature Distributions in a Scaled-Down Model of the Inlet Plenum of the SNR-300 Reactor

J. F. L. M. Brukx, G. P. R. Hansen, P. Voj

Nuclear Technology / Volume 33 / Number 1 / April 1977 / Pages 5-16

Technical Paper / Reactor / dx.doi.org/10.13182/NT77-A31759

Experimental Verification of a Method for Simulating a Boiling Water Reactor Core Based on a Few-Group Coarse-Mesh Diffusion Scheme

Sadao Uchikawa

Nuclear Technology / Volume 33 / Number 1 / April 1977 / Pages 17-29

Technical Paper / Reactor / dx.doi.org/10.13182/NT77-A31760

Plutonium Release from Burning Sodium

J. L. Stakebake, H. N. Robinson

Nuclear Technology / Volume 33 / Number 1 / April 1977 / Pages 30-39

Technical Paper / Reactor / dx.doi.org/10.13182/NT77-A31761

Experimental Investigation of Fuel-Coolant Interaction

Wiktor Śyszkowski

Nuclear Technology / Volume 33 / Number 1 / April 1977 / Pages 40-59

Technical Paper / Fuel / dx.doi.org/10.13182/NT77-A31762

Analysis of the Venting System of the Gas-Cooled Fast Breeder Reactor Fuel Element for Various Operating Conditions

Klaus W. Klein

Nuclear Technology / Volume 33 / Number 1 / April 1977 / Pages 60-67

Technical Paper / Fuel / dx.doi.org/10.13182/NT77-A31763

Preparation and Characterization of Sintered Glass-Ceramics from Calcined Simulated High-Level Waste

E. G. Samsel, J. R. Berreth

Nuclear Technology / Volume 33 / Number 1 / April 1977 / Pages 68-75

Technical Paper / Radioactive Waste / dx.doi.org/10.13182/NT77-A31764

Mechanical Properties of Liquid-Metal Fast Breeder Reactor Primary Piping Materials

Charles R. Brinkman, Vinod K. Sikka, Roy T. King

Nuclear Technology / Volume 33 / Number 1 / April 1977 / Pages 76-95

Technical Paper / Material / dx.doi.org/10.13182/NT77-A31765

Modification of the Existing Yielding Creep Theory of Irradiation Creep in Zirconium and Zircaloy-2

P. K. Madden, R. V. Hesketh

Nuclear Technology / Volume 33 / Number 1 / April 1977 / Pages 96-102

Technical Paper / Material / dx.doi.org/10.13182/NT77-A31766

Neutron Flux Measurement at the LAMPF Radiation Effects Facility

Dennis G. Perry, Margaret L. Simmons, James S. Gilmore

Nuclear Technology / Volume 33 / Number 1 / April 1977 / Pages 103-109

Technical Paper / Accelerator / dx.doi.org/10.13182/NT77-A31767

Comment on the Interpretation and Application of Limiting Critical Concentrations of Fissile Nuclides in Water

E. D. Clayton, B. M. Durst

Nuclear Technology / Volume 33 / Number 1 / April 1977 / Pages 110-111

Technical Note / Chemical Processing / dx.doi.org/10.13182/NT77-A31768

The Effect of Chemistry Variations on the Short-Term Rupture Life and Tensile Properties of 20% Cold-Worked Type 316 Stainless Steel

D. R. Duncan, M. M. Paxton

Nuclear Technology / Volume 33 / Number 1 / April 1977 / Pages 112-119

Technical Note / Material / dx.doi.org/10.13182/NT77-A31769

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