ANS / Publications / Journals / Nuclear Technology

Fault-Tree Analysis of Criticality in a Pulsed Column of a Typical Reprocessing Facility

Yasushi Nomura, Yoshitaka Naito

Nuclear Technology / Volume 121 / Number 1 / January 1998 / Pages 3-13

Technical Paper / Kiyose Birthday Anniversary / dx.doi.org/10.13182/NT98-A2814

Study on the Permeability of Engineered Barriers for the Enhancement of a Radioactive Waste Repository System

Shingo Tashiro, Ai Fujiwara, Muneaki Senoo

Nuclear Technology / Volume 121 / Number 1 / January 1998 / Pages 14-23

Technical Paper / Kiyose Birthday Anniversary / dx.doi.org/10.13182/NT98-A2815

Integrated Radionuclide Transport Model for a High-Level Waste Repository in Water-Saturated Geologic Formations

Joonhong Ahn

Nuclear Technology / Volume 121 / Number 1 / January 1998 / Pages 24-39

Technical Paper / Kiyose Birthday Anniversary / dx.doi.org/10.13182/NT121-24

Stability of Natural Circulation Boiling Water Reactors: Part I - Description Stability Model and Theoretical Analysis in Terms of Dimensionless Groups

David D. B. van Bragt, Tim H. J. J. van der Hagen

Nuclear Technology / Volume 121 / Number 1 / January 1998 / Pages 40-51

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT98-A2817

Stability of Natural Circulation Boiling Water Reactors: Part II - Parametric Study of Coupled Neutronic-Thermohydraulic Stability

David D. B. van Bragt, Tim H. J. J. van der Hagen

Nuclear Technology / Volume 121 / Number 1 / January 1998 / Pages 52-62

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT98-A2818

Self-Diffusion of Sodium Ions in Compacted Sodium Montmorillonite

Tamotsu Kozaki, Atsushi Fujishima, Seichi Sato, Hiroshi Ohashi

Nuclear Technology / Volume 121 / Number 1 / January 1998 / Pages 63-69

Technical Paper / Criticality of Nuclear Materials / dx.doi.org/10.13182/NT98-A2819

Probabilistic Model of Iodine Release for Steam Generator Tube Primary-to-Secondary Leakage Induced by Main Steam-Line Break

Peter S. Jackson, Patrick J. Williams

Nuclear Technology / Volume 121 / Number 1 / January 1998 / Pages 70-80

Technical Paper / Human Factors / dx.doi.org/10.13182/NT98-A2820

Control of a Fast Reactor Cooled by Supercritical Light Water

Tohru Nakatsuka, Yoshiaki Oka, Seiichi Koshizuka

Nuclear Technology / Volume 121 / Number 1 / January 1998 / Pages 81-92

Technical Paper / Reactor Operations and Control / dx.doi.org/10.13182/NT98-A2821

Fifteen Years of Research and Development on Direct Disposal in Germany: An Overview

Klaus-Detlef Closs, Reiner Papp

Nuclear Technology / Volume 121 / Number 2 / February 1998 / Pages 101-113

Technical Paper / German Direct Disposal Project / dx.doi.org/10.13182/NT98-A2822

An Assessment of the Results of the Direct Disposal Project by the Federal Ministry for the Environment, Nature Conservation, and Nuclear Safety

Manfred Bloser, Thomas Beuth

Nuclear Technology / Volume 121 / Number 2 / February 1998 / Pages 114-119

Technical Paper / German Direct Disposal Project / dx.doi.org/10.13182/NT98-A2823

Evaluation of Direct Disposal from the Point of View of One Utility and Perspectives for Waste Management

Wolfgang Heni

Nuclear Technology / Volume 121 / Number 2 / February 1998 / Pages 120-127

Technical Paper / German Direct Disposal Project / dx.doi.org/10.13182/NT98-A2824

Status of the Gorleben Pilot Conditioning Plant

Hans-Otto Willax

Nuclear Technology / Volume 121 / Number 2 / February 1998 / Pages 128-135

Technical Paper / German Direct Disposal Project / dx.doi.org/10.13182/NT98-A2825

Status of the Development of Final Disposal Casks and Prospects in Germany

Klaus Janberg, Harry Spilker

Nuclear Technology / Volume 121 / Number 2 / February 1998 / Pages 136-147

Technical Paper / German Direct Disposal Project / dx.doi.org/10.13182/NT98-A2826

Conceptual Design and Demonstration Tests for Disposal of Spent Fuel in a Salt Repository

Hans-Jürgen Engelmann

Nuclear Technology / Volume 121 / Number 2 / February 1998 / Pages 148-161

Technical Paper / German Direct Disposal Project / dx.doi.org/10.13182/NT98-A2827

International Nuclear Material Safeguards for the Direct Final Disposal of Spent-Fuel Assemblies

Bernd Richter

Nuclear Technology / Volume 121 / Number 2 / February 1998 / Pages 162-167

Technical Paper / German Direct Disposal Project / dx.doi.org/10.13182/NT98-A2828

Retrievability of Spent Nuclear Fuel After Final Disposal in a Salt Dome

Enrique A. Biurrun

Nuclear Technology / Volume 121 / Number 2 / February 1998 / Pages 168-173

Technical Paper / German Direct Disposal Project / dx.doi.org/10.13182/NT98-A2829

Long-Term Stability of Spent Nuclear Fuel Waste Packages in Gorleben Salt Repository Environments

Bernd Grambow, Andreas Loida, Emmanuel Smailos

Nuclear Technology / Volume 121 / Number 2 / February 1998 / Pages 174-188

Technical Paper / German Direct Disposal Project / dx.doi.org/10.13182/NT98-A2830

Special Safety Aspects of Drift Disposal - The Thermal Simulation of the Drift Storage Experiment

Tilmann Rothfuchs, Johannes Droste, Hans-Karl Feddersen, Stefan Heusermann, Jörn U. Schneefuss, Alexandra Pudewills

Nuclear Technology / Volume 121 / Number 2 / February 1998 / Pages 189-198

Technical Paper / German Direct Disposal Project / dx.doi.org/10.13182/NT98-A2831

Evaluation of Repository Concepts for the Disposal of Spent Fuel on the Basis of Geotechnical Safety Indicators and Exploration Data

Michael Langer, Manfred Wallner

Nuclear Technology / Volume 121 / Number 2 / February 1998 / Pages 199-211

Technical Paper / German Direct Disposal Project / dx.doi.org/10.13182/NT98-A2832

A Comparison of Long-Term Safety Aspects - Concepts for Disposal of Spent Fuel and Wastes from Reprocessing

Richard Storck, Dieter Buhmann

Nuclear Technology / Volume 121 / Number 2 / February 1998 / Pages 212-220

Technical Paper / German Direct Disposal Project / dx.doi.org/10.13182/NT98-A2833

Further Development Work for a Future Gorleben Repository

Jürgen P. Lempert

Nuclear Technology / Volume 121 / Number 2 / February 1998 / Pages 221-226

Technical Paper / German Direct Disposal Project / dx.doi.org/10.13182/NT98-A2834

Overview of Electric Power Research Institute Nuclear Safety Analysis Activities

Lance J. Agee

Nuclear Technology / Volume 121 / Number 3 / March 1998 / Pages 229-236

Technical Paper / RETRAN / dx.doi.org/10.13182/NT98-A2835

Validation of the Laguna Verde RETRAN-03 Model for Pressurization Transients

Jorge Solis-Rodarte, Juan Carlos Ramos, Enrique Salaices

Nuclear Technology / Volume 121 / Number 3 / March 1998 / Pages 237-244

Technical Paper / RETRAN / dx.doi.org/10.13182/NT98-A2836

Simulation of a BWR-5 Plant: Verification and Validation of RETRAN-03

Michitsugu Mori

Nuclear Technology / Volume 121 / Number 3 / March 1998 / Pages 245-259

Technical Paper / RETRAN / dx.doi.org/10.13182/NT98-A2837

Benchmarking and Qualification of RETRAN-03 for BWR Stability Analysis by Comparison with Frequency-Domain Stability Analysis Code

Michitsugu Mori

Nuclear Technology / Volume 121 / Number 3 / March 1998 / Pages 260-274

Technical Paper / RETRAN / dx.doi.org/10.13182/NT98-A2838

Cofrentes Reload Licensing Methodology with RETRAN-03

Pedro Mata, Rafael de la Fuente, Pablo G. Sedano, Juan Serra

Nuclear Technology / Volume 121 / Number 3 / March 1998 / Pages 275-288

Technical Paper / RETRAN / dx.doi.org/10.13182/NT98-A2839

TU Electric's Experiences with the Development and NRC Approval of a Reload Safety Analysis Methodology

W. James Boatwright, David W. Hiltbrand, Whee G. Choe

Nuclear Technology / Volume 121 / Number 3 / March 1998 / Pages 289-294

Technical Paper / RETRAN / dx.doi.org/10.13182/NT98-A2840

Steam Generator Tube Plugging and Replacement Analyses for McGuire and Catawba

Gregg B. Swindlehurst

Nuclear Technology / Volume 121 / Number 3 / March 1998 / Pages 295-301

Technical Paper / RETRAN / dx.doi.org/10.13182/NT98-A2841

Plant-Specific RETRAN Analyses in Support of Chinshan BWR/4 Operation

Jan-Ru Tang, Lainsu Kao, Der-Yeong Shiau, Lin-Yao Chou, Ching-Chuan Yao, Show-Chyuan Chiang

Nuclear Technology / Volume 121 / Number 3 / March 1998 / Pages 302-312

Technical Paper / RETRAN / dx.doi.org/10.13182/NT98-A2842

Calculation of BWR Shroud Head Loads and Axial Lift During a Main Steam-Line Break

John M. Sorensen, Nicholas G. Trikouros

Nuclear Technology / Volume 121 / Number 3 / March 1998 / Pages 313-323

Technical Paper / RETRAN / dx.doi.org/10.13182/NT98-A2843

Thermal-Hydraulic Analysis of Core Shroud Crack for Chinshan BWR/4 Unit 2 Using RETRAN-02/MOD5

Jan-Ru Tang, Lainsu Kao, Der-Yeong Shiau, Lin-Yao Chou, Ching-Chuan Yao, Show-Chyuan Chiang

Nuclear Technology / Volume 121 / Number 3 / March 1998 / Pages 324-336

Technical Paper / RETRAN / dx.doi.org/10.13182/NT98-A2844

Detectability of BWR Core Shroud Separation Through Anomalous Core Characteristics

Hiroshi Kawai, Ichio Tomiai

Nuclear Technology / Volume 121 / Number 3 / March 1998 / Pages 337-345

Technical Paper / RETRAN / dx.doi.org/10.13182/NT98-A2845

Realistic Scoping Study of Reactivity Insertion Accidents for Typical PWR and BWR Cores

Antonio F. Dias, Laurance D. Eisenhart, Ronald E. Engel, Lance J. Agee

Nuclear Technology / Volume 121 / Number 3 / March 1998 / Pages 346-358

Technical Paper / RETRAN / dx.doi.org/10.13182/NT98-A2846