Home / Publications / Journals / Nuclear Technology / Volume 11 / Number 4

Volume 11

Number 4

Table of Contents
Authors(P. L. Rittenhouse, R. A. Dean, A. D. Emery, D. B. Scott, J. R. Stewart, D. O. Hobson, M. F. Osborne, G. W. Parker, R. D. Waddell, Jr., F. A. Lorenz, D. O. Hobson, G. W. Parker, B. E. Bingham, A. L. Lowe, Jr., Wayne A. Carbiener, Richard G. Bock, John D. Duncan, James E. Leonard, J. E. Hench, D. J. Liffengren, P. R. Davis, J. O. Cermak, R. H. Leyse, D. P. Dominicis, John T. Mihalczo, Jon A. Reuscher, R. M. Carroll, O. Sisman, C. Z. Serpan, Jr., H. E. Watson, R. M. Collins, R. D. Baybarz, J. B. Knauer, J. R. Peterson)
Preface: Symposium on Fuel Rod Failure and Its Effects(P. L. Rittenhouse, R. A. Dean)

Effects of Heating Rate and Pressure on Expansion of Zircaloy Tubing During Sudden Heating Conditions

A. D. Emery, D. B. Scott, J. R. Stewart

Nuclear Technology / Volume 11 / Number 4 / August 1971 / Pages 474-478

Technical Paper / Symposium on Fuel Rod Failure and Its Effect / Fuel / dx.doi.org/10.13182/NT71-A30844

Comparison of Rupture Data from Irradiated Fuel Rods and Unirradiated Cladding

D. O. Hobson, M. F. Osborne, G. W. Parker

Nuclear Technology / Volume 11 / Number 4 / August 1971 / Pages 479-490

Technical Paper / Symposium on Fuel Rod Failure and Its Effect / Fuel / dx.doi.org/10.13182/NT71-A30845

Measurement of Light-Water Reactor Coolant Channel Reduction Arising from Cladding Deformation During a Loss-of-Coolant Accident

R. D. Waddell, Jr.

Nuclear Technology / Volume 11 / Number 4 / August 1971 / Pages 491-501

Technical Paper / Symposium on Fuel Rod Failure and Its Effect / Fuel / dx.doi.org/10.13182/NT71-A30846

Fuel Rod Failure Under Loss-of-Coolant Conditions in Treat

R. A. Lorenz, D. O. Hobson, G. W. Parker

Nuclear Technology / Volume 11 / Number 4 / August 1971 / Pages 502-520

Technical Paper / Symposium on Fuel Rod Failure and Its Effect / Fuel / dx.doi.org/10.13182/NT71-A30847

Application of Experimental Data to Analytical Evaluation of Cladding Failure Distribution

B. E. Bingham, A. L. Lowe, Jr.

Nuclear Technology / Volume 11 / Number 4 / August 1971 / Pages 521-525

Technical Paper / Symposium on Fuel Rod Failure and Its Effect / Fuel / dx.doi.org/10.13182/NT71-A30848

The Effects of Clad Swelling on Emergency Core Cooling Performance

Wayne A. Carbiener

Nuclear Technology / Volume 11 / Number 4 / August 1971 / Pages 526-531

Technical Paper / Symposium on Fuel Rod Failure and Its Effect / Fuel / dx.doi.org/10.13182/NT71-A30849

The Effect of Zircaloy-Clad Fuel Rod Failure on BWR Core Spray Cooling

Richard G. Bock, John D. Duncan, James E. Leonard

Nuclear Technology / Volume 11 / Number 4 / August 1971 / Pages 532-543

Technical Paper / Symposium on Fuel Rod Failure and Its Effect / Fuel / dx.doi.org/10.13182/NT71-A30850

The Effect of Fuel Rod Failure on Emergency Core Cooling System Design for Boiling Water Reactors

J. E. Hench, D. J. Liffengren

Nuclear Technology / Volume 11 / Number 4 / August 1971 / Pages 544-550

Technical Paper / Symposium on Fuel Rod Failure and Its Effect / Fuel / dx.doi.org/10.13182/NT71-A30851

Experimental Studies of The Effect of Flow Restrictions in a Small Rod Bundle Under Emergency Core Coolant Injection Conditions

P. R. Davis

Nuclear Technology / Volume 11 / Number 4 / August 1971 / Pages 551-556

Technical Paper / Symposium on Fuel Rod Failure and Its Effect / Fuel / dx.doi.org/10.13182/NT71-A30852

Effect of Flow Blockage on Bottom Flooding Heat Transfer Effectiveness (Flecht)

J. O. Cermak, R. H. Leyse, D. P. Dominicis

Nuclear Technology / Volume 11 / Number 4 / August 1971 / Pages 557-562

Technical Paper / Symposium on Fuel Rod Failure and Its Effect / Fuel / dx.doi.org/10.13182/NT71-A30853

Dynamic Neutronic and Mechanical Measurements with a Pulse Reactor of Uranium-Molybdenum Alloy

John T. Mihalczo, Jon A. Reuscher

Nuclear Technology / Volume 11 / Number 4 / August 1971 / Pages 563-577

Technical Paper / Symposium on Fuel Rod Failure and Its Effect / Reactor / dx.doi.org/10.13182/NT71-A30854

Behavior of Mixed Oxide (U,Pu)O₂ Fuels as a Function of Temperature and Burnup

R. M. Carroll, O. Sisman

Nuclear Technology / Volume 11 / Number 4 / August 1971 / Pages 578-591

Technical Paper / Symposium on Fuel Rod Failure and Its Effect / Fuel / dx.doi.org/10.13182/NT71-A30855

Through-Thickness Neutron Fluence and Embrittlement Gradients in Reactor Pressure Vessels

C. Z. Serpan, Jr., H. E. Watson

Nuclear Technology / Volume 11 / Number 4 / August 1971 / Pages 592-601

Technical Paper / Symposium on Fuel Rod Failure and Its Effect / Material / dx.doi.org/10.13182/NT71-A30856

Underwater Charging Machine for Nuclear Irradiation Sample Insertion

R. M. Collins

Nuclear Technology / Volume 11 / Number 4 / August 1971 / Pages 602-608

Technical Paper / Symposium on Fuel Rod Failure and Its Effect / Hot Laboratory / dx.doi.org/10.13182/NT71-A30857

New Encapsulation Techniques for the Fabrication of Californium-252 Neutron Sources

R. D. Baybarz, J. B. Knauer, J. R. Peterson

Nuclear Technology / Volume 11 / Number 4 / August 1971 / Pages 609-615

Technical Paper / Symposium on Fuel Rod Failure and Its Effect / Technique / dx.doi.org/10.13182/NT71-A30858