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Home / Publications / Journals / Nuclear Technology / Volume 108 / Number 3

Volume 108

Number 3

Cross-Section Parameterization Using Irradiation Time and Exposure for Global Depletion Analysis

Steven E. Aumeier, John C. Lee, Derek M. Cribley, William R. Martin

Nuclear Technology / Volume 108 / Number 3 / December 1994 / Pages 299-319

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT94-A35014

Rough Estimates of Severe Accident Containment Loads Accompanying Vessel Breach in Boiling Water Reactors

Mark T. Leonard

Nuclear Technology / Volume 108 / Number 3 / December 1994 / Pages 320-337

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT94-A35015

Analysis of a Core Disruptive Accident in a Liquid-Metal-Cooled Fast Breeder Reactor Using the Near-Characteristic Method

Jayan K. George, Jagdeep B. Doshi

Nuclear Technology / Volume 108 / Number 3 / December 1994 / Pages 338-349

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT94-A35016

Stability Measurements in the German Nuclear Power Plant Wuergassen During Cycle 14

Ethwart Pollmann, Joachim Schulze, Dieter Kreuter

Nuclear Technology / Volume 108 / Number 3 / December 1994 / Pages 350-360

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT94-A35017

Chinese Experience in the Removal of Actinides from Highly Active Waste by Trialkylphosphine-Oxide Extraction

Yongjun Zhu, Rongzhou Jiao

Nuclear Technology / Volume 108 / Number 3 / December 1994 / Pages 361-369

Technical Paper / Enrichment and Reprocessing System / dx.doi.org/10.13182/NT94-A35018

Development of a Demister for a Waste Evaporator Using a Hydrophobic Membrane Filter

Kiyomi Funabashi, Koichi Chino, Tsutomu Baba, Hiroyuki Tsuchiya, Tatsuo Izumida, Toshio Sawa

Nuclear Technology / Volume 108 / Number 3 / December 1994 / Pages 370-378

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT94-A35019

The Benchmarking of a Homogeneous Equilibrium Model for Analysis of Spent-Fuel Shipping Containers

Steven J. Manson, Dale E. Klein

Nuclear Technology / Volume 108 / Number 3 / December 1994 / Pages 379-386

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT94-A35020

RELAP5/MOD3 Modeling of Water Column Rejoining and a Water Slug Propelled by Noncondensable Gas

W. S. Yeung, J. Shirkov, F. Seifaee

Nuclear Technology / Volume 108 / Number 3 / December 1994 / Pages 387-394

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT94-A35021

Validation of the ATR-SINDA Fuel Plate Model Using Advanced Test Reactor Startup Data

Steven T. Polkinghorne

Nuclear Technology / Volume 108 / Number 3 / December 1994 / Pages 395-412

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT94-A35022

A Transient Analysis of Decomposition and Erosion of Concrete Exposed to a Surface Heat Flux

Arif Nesimi Kiliç

Nuclear Technology / Volume 108 / Number 3 / December 1994 / Pages 413-420

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT94-A35023

Maximum Likelihood Factor Analysis of the Reactor Coolant Pump System

William S. Grenzebach, Carolyn D. Heising, Thomas J. Marx

Nuclear Technology / Volume 108 / Number 3 / December 1994 / Pages 421-433

Technical Paper / Reactor Operation / dx.doi.org/10.13182/NT94-A35024

 

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