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Volume 85

Number 3

  • Table of Contents
  • Authors(Karen H. Koger, M. Jonathan Haire, Brett L. Humphrys, Jay F. Manneschmidt, Keiichi Setoguchi, Ryodai Nakai, Kazunori Sasaki, Naotaka Terashita, Takamichi Ogino, Makoto Osaki, Akira Kanagawa, Jan-Li Wang, Jay F. Kunze, L. C. Lewis, J. P. Henscheid, Mukesh Tayal, Lorne D. Macdonald, Erl Kohn, Walter P. Dovigo, T. Sampat Sridhar, Michael P. Manahan, Xiangdong Feng, Ian L. Pegg, Aaron Barkatt, Pedro B. Macedo, Samuel J. Cucinell, Shantao Lai, R. K. S. Rathore, P. Munshi, P. Arora, S. D. Malik, A. K. Vaish, K. S. Singh, U. Singh)

The Centralized Reliability Data Organization (CREDO) Assessment of Critical Component Unavailability in Liquid-Metal Reactors

Karen H. Koger, M. Jonathan Haire, Brett L. Humphrys, Jay F. Manneschmidt, Keiichi Setoguchi, Ryodai Nakai

Nuclear Technology / Volume 85 / Number 3 / June 1989 / Pages 251-258

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT89-A34247

The Development of the Fast-Running Simulation Pressurized Water Reactor Plant Analyzer Code (NUPAC-1)

Kazunori Sasaki, Naotaka Terashita, Takamichi Ogino

Nuclear Technology / Volume 85 / Number 3 / June 1989 / Pages 259-273

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT89-A34248

Performance of High-Efficiency Particulate Air Filters Under Severe Conditions

Makoto Osaki, Akira Kanagawa

Nuclear Technology / Volume 85 / Number 3 / June 1989 / Pages 274-284

Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT89-A34249

Using the RELAP5/MOD2 Code Under Low-Pressure/Low-Temperature Loss-of-Coolant-Accident Conditions

Jan-Li Wang, Jay F. Kunze

Nuclear Technology / Volume 85 / Number 3 / June 1989 / Pages 285-293

Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT89-A34250

The Performance of the Remote Analytical Laboratory During the First Fluorinel Dissolution Process Campaign

L. C. Lewis, J. P. Henscheid

Nuclear Technology / Volume 85 / Number 3 / June 1989 / Pages 294-299

Technical Paper / Chemical Processing / dx.doi.org/10.13182/NT89-A34251

A Model for the Transient Release of Fission Products from UO2 Fuel: Gasout Code Description

Mukesh Tayal, Lorne D. Macdonald, Erl Kohn, Walter P. Dovigo

Nuclear Technology / Volume 85 / Number 3 / June 1989 / Pages 300-313

Technical Paper / Nuclear Fuel / dx.doi.org/10.13182/NT89-A34252

High-Level Liquid Waste Treatment: Process Development Studies in the WIPE Facility—Part I

T. Sampat Sridhar

Nuclear Technology / Volume 85 / Number 3 / June 1989 / Pages 314-323

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT89-A34253

Determining the Physical Properties of Steam Generator Tube Scale Using Miniature Specimens

Michael P. Manahan

Nuclear Technology / Volume 85 / Number 3 / June 1989 / Pages 324-333

Technical Paper / Material / dx.doi.org/10.13182/NT89-A34254

Correlation Between Composition Effects on Glass Durability and the Structural Role of the Constituent Oxides

Xiangdong Feng, Ian L. Pegg, Aaron Barkatt, Pedro B. Macedo, Samuel J. Cucinell, Shantao Lai

Nuclear Technology / Volume 85 / Number 3 / June 1989 / Pages 334-345

Technical Paper / Material / dx.doi.org/10.13182/NT89-A34255

A New Non-Fourier Tomographic Filter for Image Reconstruction

R. K. S. Rathore, P. Munshi, P. Arora, S. D. Malik, A. K. Vaish, K. S. Singh, U. Singh

Nuclear Technology / Volume 85 / Number 3 / June 1989 / Pages 346-349

Technical Paper / Technique / dx.doi.org/10.13182/NT89-A34256