American Nuclear Society
Home

Home / Publications / Journals / Nuclear Technology / Volume 76 / Number 2

Volume 76

Number 2

Determination of Isotopic Ratios from Fuel Burnup

John C. Lee, Sin Tao Hsue

Nuclear Technology / Volume 76 / Number 2 / February 1987 / Pages 203-208

Technical Paper / Fuel Cycle / dx.doi.org/10.13182/NT87-A33874

ELOCA-A: A Code for Radial and Axial Behavior of CANDU Fuel Elements at High Temperatures

Mukesh Tayal, Ed Mischkot, Harve E. Sills, A. W. L. Segel

Nuclear Technology / Volume 76 / Number 2 / February 1987 / Pages 209-220

Technical Paper / Nuclear Fuel / dx.doi.org/10.13182/NT87-A33875

Properties of Bentonite Clay as Buffer Material in High-Level Waste Geological Disposal. Part I: Chemical Species Contained in Bentonite

Masanori Takahashi, Masayuki Muroi, Atsuyuki Inoue, Masahiro Aoki, Makoto Takizawa, Kenkichi Ishigure, Norihiko Fujita

Nuclear Technology / Volume 76 / Number 2 / February 1987 / Pages 221-228

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT87-A33876

An Experimental Correlation of Cross-Flow Pressure Drop for Triangular Array Wire-Wrapped Rod Assemblies

Kune Yull Suh, Neil E. Todreas

Nuclear Technology / Volume 76 / Number 2 / February 1987 / Pages 229-240

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT87-A33877

In Vivo Measurement of Organ Mercury by Prompt Gamma Activation Analysis Using a Mobile Nuclear Reactor

Pao-Shu Chang, Yau-Hui ho, Chien Chung, Liq-Ji Yuan, Pao-Shan Weng

Nuclear Technology / Volume 76 / Number 2 / February 1987 / Pages 241-247

Technical Paper / Analyse / dx.doi.org/10.13182/NT87-A33878

Simulation of the Transient Response of Ionization Chambers to Bias Voltage Perturbations

Tunc Aldemir, Steven A. Arndt, Don. W. Miller

Nuclear Technology / Volume 76 / Number 2 / February 1987 / Pages 248-259

Technical Paper / Technique / dx.doi.org/10.13182/NT87-A33879

The Formation of Surface Layers and Reaction Products in the Leaching of Defense Borosilicate Nuclear Waste Glass

Alan B. Harker, John F. Flintoff

Nuclear Technology / Volume 76 / Number 2 / February 1987 / Pages 263-275

Performance of Borosilicate Glass High-Level Waste Forms in Disposal Systems / Radioactive Waste Management / dx.doi.org/10.13182/NT87-A33880

A Guillotine Tube Rupture Modeling Technique Using RETRAN-02

Peter J. Jensen, James F. Lang, Jason Chao

Nuclear Technology / Volume 76 / Number 2 / February 1987 / Pages 279-289

Fourth International Retran Meeting / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT87-A33881

A Parametric Study of an Anticipated Transient Without Scram in a Westinghouse Four-Loop Plant

Peter J. Jensen, Kent D. Richert, Jason Chao

Nuclear Technology / Volume 76 / Number 2 / February 1987 / Pages 290-302

Fourth International Retran Meeting / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT87-A33882

Moderator Feedback Effects in Two-Dimensional Nodal Methods for Pressurized Water Reactor Analysis

Thomas J. Downar

Nuclear Technology / Volume 76 / Number 2 / February 1987 / Pages 303-307

Technical Note / Fission Reactor / dx.doi.org/10.13182/NT87-A33883