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Volume 71

Number 2

Table of Contents
Authors(Mamdouh Shoukri, Abd-el-elah Tahir, Michael B. Carver, Mark L. Williams, R. Q. Wright, Brian A. Worley, Odelli Ozer, Walter J. Eich, Yukiharu Ohga, Kohyu Fukunishi, Om Pal Singh, P. Bhaskar Rao, O. K. Tallent, J. C. Mailen, K. E. Dodson, James L. Kelly, Robert U. Mulder, Chaim J. Babad, Roderick D. MacDonald, Ian J. Hastings, Gary S. Was, Ronald Christensen, Chang Park, Richard W. Smith, Ivars Neretnieks, Craig L. Timmerman, Ken H. Oma, Alexander P. Murray, David A. Eckhardt, Sharon L. Weisberg, M. O. Menlove, J. E. Swansen, Minsun Ouyang, Martin E. Nelson, Dean A. Miller, Peter F. Wiggins, Gordon Riel, Thomas D. Strickler)

Numerical Simulation of Two-Phase Flow in Horizontal Interconnected Subchannels

Mamdouh Shoukri, Abd-El-Elah Tahir, Michael B. Carver

Nuclear Technology / Volume 71 / Number 2 / November 1985 / Pages 375-385

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT85-A33690

Analysis of Thermal Reactor Benchmarks with Design Codes Based on ENDF/B-V Data

Mark L. Williams, R. Q. Wright, Brian A. Worley, Odelli Ozer, Walter J. Eich

Nuclear Technology / Volume 71 / Number 2 / November 1985 / Pages 386-401

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT85-A33691

A Reactor Water Level and Pressure Prediction Method Under Small Loss-of-Coolant-Accident Conditions in Boiling Water Reactors

Yukiharu Ohga, Kohyu Fukunishi

Nuclear Technology / Volume 71 / Number 2 / November 1985 / Pages 402-410

Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT85-A33692

Dynamics of Fuel Vapor Pressure Buildup in Voided LMFBR Cores During the Transient Heating and Its Effect on the Energy Release in a Core Disruptive Accident

Om Pal Singh, P. Bhaskar Rao

Nuclear Technology / Volume 71 / Number 2 / November 1985 / Pages 411-416

Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT85-A33693

Purex Diluent Chemical Degradation

O. K. Tallent, J. C. Mailen, K. E. Dodson

Nuclear Technology / Volume 71 / Number 2 / November 1985 / Pages 417-425

Technical Paper / Chemical Processing / dx.doi.org/10.13182/NT85-A33694

Experimental Investigation of the Iodine Partition Coefficient

James L. Kelly, Robert U. Mulder, Chaim J. Babad

Nuclear Technology / Volume 71 / Number 2 / November 1985 / Pages 426-429

Technical Paper / Chemical Processing / dx.doi.org/10.13182/NT85-A33695

Graphite Disk UO₂ Fuel Elements Designed for Extended Burnups at High Powers

Roderick D. MacDonald, Ian J. Hastings

Nuclear Technology / Volume 71 / Number 2 / November 1985 / Pages 430-444

Technical Paper / Nuclear Fuel / dx.doi.org/10.13182/NT85-A33696

Statistical Patterns of Fuel Failure in Stainless Steel Clad Light Water Reactor Fuel Rods

Gary S. Was, Ronald Christensen, Chang Park, Richard W. Smith

Nuclear Technology / Volume 71 / Number 2 / November 1985 / Pages 445-457

Technical Paper / Nuclear Fuel / dx.doi.org/10.13182/NT85-A33697

Diffusivities of Some Constituents in Compacted Wet Bentonite Clay and the Impact on Radionuclide Migration in the Buffer

Ivars Neretnieks

Nuclear Technology / Volume 71 / Number 2 / November 1985 / Pages 458-470

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT85-A33698

A Pilot-Scale Radioactive Test Using In Situ Vitrification

Craig L. Timmerman, Ken H. Oma

Nuclear Technology / Volume 71 / Number 2 / November 1985 / Pages 471-481

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT85-A33699

Dilute Chemical Decontamination Process for Pressurized and Boiling Water Reactor Applications

Alexander P. Murray, David A. Eckhardt, Sharon L. Weisberg

Nuclear Technology / Volume 71 / Number 2 / November 1985 / Pages 482-496

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT85-A33700

A High-Performance Neutron Time Correlation Counter

H. O. Menlove, J. E. Swansen

Nuclear Technology / Volume 71 / Number 2 / November 1985 / Pages 497-505

Technical Paper / Analyses / dx.doi.org/10.13182/NT85-A33701

An Iterative Correction Method for Nondestructive Plutonium Waste Assay

Minsun Ouyang

Nuclear Technology / Volume 71 / Number 2 / November 1985 / Pages 506-511

Technical Paper / Analyses / dx.doi.org/10.13182/NT85-A33702

Computer Graphics to Separate Neutron from Gamma-Ray Spectra, Applied to the Measurement of Neutron Attenuation Coefficients Using an NE-213 Scintillator

Martin E. Nelson, Dean A. Miller, Peter F. Wiggins, Gordon Riel, Thomas D. Strickler

Nuclear Technology / Volume 71 / Number 2 / November 1985 / Pages 512-519

Technical Paper / Technique / dx.doi.org/10.13182/NT85-A33703

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