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Volume 102

Number 1

Table of Contents
Comments on “Failure Probability of Axially Cracked Steam Generator Tubes: A Probabilistic Fracture Mechanics Model”(J. Hopenfeld)
Response to “Comments on ‘Failure Probability of Axially Cracked Steam Generator Tubes: A Probabilistic Fracture Mechanics Model’”(B. Mavko, L. Cizelj)

Development of Mixed-Oxide Fuel Manufacture in the United Kingdom and the Influence of Fuel Characteristics on Irradiation Performance

Hugh M. MacLeod, Geoffrey Yates

Nuclear Technology / Volume 102 / Number 1 / April 1993 / Pages 3-17

Technical Paper / Mixed-Oxide Fuel / Nuclear Fuel Cycle / dx.doi.org/10.13182/NT93-A34798

Plutonium Processing at the Siemens Hanau Fuel Fabrication Plant

Jürgen Krellmann

Nuclear Technology / Volume 102 / Number 1 / April 1993 / Pages 18-28

Technical Paper / Mixed-Oxide Fuel / Enrichment and Reprocessing System / dx.doi.org/10.13182/NT93-A34799

Irradiation Behavior of UO₂/PuO₂ Fuel in Light Water Reactors

Wolfgang Goll, Hans-Peter Fuchs, Reiner Manzel, Fritz U. Schlemmer

Nuclear Technology / Volume 102 / Number 1 / April 1993 / Pages 29-46

Technical Paper / Mixed-Oxide Fuel / Nuclear Fuel Cycle / dx.doi.org/10.13182/NT93-A34800

In-Pile Performance of Mixed-Oxide Fuel with Particular Emphasis on MIMAS Fuel

P. Deramaix, D. Haas, J. Van De Velde

Nuclear Technology / Volume 102 / Number 1 / April 1993 / Pages 47-53

Technical Paper / Mixed-Oxide Fuel / Nuclear Fuel Cycle / dx.doi.org/10.13182/NT93-A34801

Experience in PWR and BWR Mixed-Oxide Fuel Management

Gerhard J. Schlosser, Wolf-Dieter Krebs, Peter Urban

Nuclear Technology / Volume 102 / Number 1 / April 1993 / Pages 54-67

Technical Paper / Mixed-Oxide Fuel / Nuclear Fuel Cycle / dx.doi.org/10.13182/NT93-A34802

Investigation of the Nuclear Inventories of High-Exposure PWR Mixed-Oxide Fuels with Multiple Recycling of Self-Generated Plutonium

Hans-Werner Wiese

Nuclear Technology / Volume 102 / Number 1 / April 1993 / Pages 68-80

Technical Paper / Mixed-Oxide Fuel / Nuclear Fuel Cycle / dx.doi.org/10.13182/NT93-A34803

Validation of Fuel Bundle Mechanical Performance Code ÉTOILE with Bundle/Duct Interaction Experimental Data

Masatoshi Nakagawa

Nuclear Technology / Volume 102 / Number 1 / April 1993 / Pages 81-89

Technical Paper / Mixed-Oxide Fuel / Fission Reactor / dx.doi.org/10.13182/NT93-A34804

Development of a Connectivity Verification System for Sequence Diagrams of Power Plants

Mitsuko Fukuda, Naoyuki Yamada, Ken’ichi Kan, Mitsugu Utsunomiya

Nuclear Technology / Volume 102 / Number 1 / April 1993 / Pages 90-99

Technical Paper / Mixed-Oxide Fuel / Fission Reactor / dx.doi.org/10.13182/NT93-A34805

Global Analysis of Bundle Behavior in Pressurized Water Reactor Specific CORA Experiments

Wolfgang Hering, Kazuo Minato, Fumihisa Nagase

Nuclear Technology / Volume 102 / Number 1 / April 1993 / Pages 100-115

Technical Paper / Mixed-Oxide Fuel / Nuclear Reactor Safety / dx.doi.org/10.13182/NT93-A34806

RELAP5/MOD2 Split Reactor Vessel Model and Steamline Break Analysis

Stojan Petelin, Borut Mavko, Oton Gortnar

Nuclear Technology / Volume 102 / Number 1 / April 1993 / Pages 116-124

Technical Paper / Mixed-Oxide Fuel / Nuclear Reactor Safety / dx.doi.org/10.13182/NT93-A34807

Ex-Core Detector Response Caused by Control Rod Misalignment Observed During Operation of the Reactor on the Nuclear Ship Mutsu

Masafumi Itagaki, Yoshinori Miyoshi, Kazuhiko Gakuhari, Noboru Okada, Tomohiro Sakai

Nuclear Technology / Volume 102 / Number 1 / April 1993 / Pages 125-136

Technical Paper / Mixed-Oxide Fuel / Reactor Operation / dx.doi.org/10.13182/NT93-A34808

Formalisms for Handling Phenomenological Uncertainties: The Concepts of Probability, Frequency, Variability, and Probability of Frequency

Stan Kaplan

Nuclear Technology / Volume 102 / Number 1 / April 1993 / Pages 137-142

Technical Note / Mixed-Oxide Fuel / Nuclear Reactor Safety / dx.doi.org/10.13182/NT93-A34809