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Volume 66

Number 3

Table of Contents
Authors(Kenji Kikuchi, Hideo Kaburaki, Konomo Sanokawa, Katsuyuki Kawaguchi, Masaaki Nemoto, Shintaro Watanabe, W. Thiele, Günter Lehnert, Marc-Olivier Borel, André Corthay, Heinz Fischli, Hans W. Fricker, Michael J. Bennett, Michael R. Houlton, Donald A. Moore, Alan I. Foster, Michael A. M. Swidzinski, J. J. Quillico, P. J. Despresles, Josef Schaefer, Detlev Stöver, Rudolf Hecker, Hans Peter Buchkremer, Rudolf Hecker, Heinz Jonas, Detlev Stöver, Uwe Zink, Hans Huschka, Guenther Luthardt, Volker E. Portscher, August Mühlratzer, Hans Zeilinger, Hans Günter Esser, Naoki Kishimoto, Tatsuhiko Tanabe, Hiroshi Araki, Heitaro Yoshida, Ryoji Watanabe, Bernd A. Thiele, Hermann Diehl, Wilhelm Ohly, Heinz Weber, James R. Lindgren, Masahide Suzuki, Kiyoshi Fukaya, Tsuneo Kodaira, Tatsuo Oku, Katsutoshi Watanabe, Tatsuo Kondo, Yutaka Ogawa, A. Alberman, G. Bley, P. Pépin, P. Soulat, Hubertus Nickel, Florian Schubert, Peter Thomas Hughes, Donald C. Allen, Erik Bodmann, Hans-Jürgen Breuer, Gerhard Raule, Manfred Rödig, Masaki Kitagawa, Hiroshi Hattori, Akira Ohtomo, Tetsuo Teramae, Junichi Hamanaka, Hiroshi Ukikusa, Heinz-Josef Penkalla, Hans-Helmut Over, Florian Schubert, Klaus Goebbels, Harald Kapitza)

Impurity Gas Effects on Friction and Wear of High-Temperature Materials for VHTRs

Kenji Kikuchi, Hideo Kaburaki, Konomo Sanokawa, Katsuyuki Kawaguchi, Masaaki Nemoto, Shintaro Watanabe

Nuclear Technology / Volume 66 / Number 3 / September 1984 / Pages 491-502

E. Friction and Wear / Status of Metallic Materials Development for Application in Advanced High-Temperature Gas-Cooled Reactor / Material / dx.doi.org/10.13182/NT84-A33471

Development of Protective Coatings Against Primary Coolant Corrosion, Friction, and Wear

W. Thiele, Günter Lehnert

Nuclear Technology / Volume 66 / Number 3 / September 1984 / Pages 503-511

E. Friction and Wear / Status of Metallic Materials Development for Application in Advanced High-Temperature Gas-Cooled Reactor / Material / dx.doi.org/10.13182/NT84-A33472

The Tribological Behavior of Tube Supports in Helium Heat Exchangers

Marc-Olivier Borel, André Corthay, Heinz Fischli, Hans W. Fricker

Nuclear Technology / Volume 66 / Number 3 / September 1984 / Pages 512-517

E. Friction and Wear / Status of Metallic Materials Development for Application in Advanced High-Temperature Gas-Cooled Reactor / Material / dx.doi.org/10.13182/NT84-A33473

Development of a Chemical Vapor Deposition Silica Coating for U.K. Advanced Gas-Cooled Nuclear Reactor Fuel Pins

Michael J. Bennett, Michael R. Houlton, Donald A. Moore, Alan I. Foster, Michael A. M. Swidzinski

Nuclear Technology / Volume 66 / Number 3 / September 1984 / Pages 518-522

E. Friction and Wear / Status of Metallic Materials Development for Application in Advanced High-Temperature Gas-Cooled Reactor / Material / dx.doi.org/10.13182/NT84-A33474

Physical Behavior of Thermal Barriers in High-Temperature Gas-Cooled Reactor Conditions

J. J. Quillico, P. J. Despresles

Nuclear Technology / Volume 66 / Number 3 / September 1984 / Pages 523-533

E. Friction and Wear / Status of Metallic Materials Development for Application in Advanced High-Temperature Gas-Cooled Reactor / Material / dx.doi.org/10.13182/NT84-A33475

Terms and Results of Hydrogen Permeation Testing of Oxide-Scaled High-Temperature Alloys

Josef Schaefer, Detlev Stöver, Rudolf Hecker

Nuclear Technology / Volume 66 / Number 3 / September 1984 / Pages 537-549

F. Hydrogen and Tritium Permeation / Status of Metallic Materials Development for Application in Advanced High-Temperature Gas-Cooled Reactor / Material / dx.doi.org/10.13182/NT84-A33476

Advances in the Development and Description of Tritium Permeation Barriers in High-Temperature Alloys

Hans Peter Buchkremer, Rudolf Hecker, Heinz Jonas, Detlev Stöver, Uwe Zink

Nuclear Technology / Volume 66 / Number 3 / September 1984 / Pages 550-561

F. Hydrogen and Tritium Permeation / Status of Metallic Materials Development for Application in Advanced High-Temperature Gas-Cooled Reactor / Material / dx.doi.org/10.13182/NT84-A33477

Protective Layers on High-Temperature Alloys Against Hydrogen Permeation

Hans Huschka, Guenther Luthardt, Volker E. Portscher

Nuclear Technology / Volume 66 / Number 3 / September 1984 / Pages 562-569

F. Hydrogen and Tritium Permeation / Status of Metallic Materials Development for Application in Advanced High-Temperature Gas-Cooled Reactor / Material / dx.doi.org/10.13182/NT84-A33478

Development of Protective Coatings to Reduce Hydrogen and Tritium Permeation

August Mühlratzer, Hans Zeilinger, Hans Günter Esser

Nuclear Technology / Volume 66 / Number 3 / September 1984 / Pages 570-577

F. Hydrogen and Tritium Permeation / Status of Metallic Materials Development for Application in Advanced High-Temperature Gas-Cooled Reactor / Material / dx.doi.org/10.13182/NT84-A33479

Hydrogen Permeation in Metals During Exposure to a Process Gas Environment

Naoki Kishimoto, Tatsuhiko Tanabe, Hiroshi Araki, Heitaro Yoshida, Ryoji Watanabe

Nuclear Technology / Volume 66 / Number 3 / September 1984 / Pages 578-594

F. Hydrogen and Tritium Permeation / Status of Metallic Materials Development for Application in Advanced High-Temperature Gas-Cooled Reactor / Material / dx.doi.org/10.13182/NT84-A33480

Investigations Into the Irradiation Behavior of High-Temperature Alloys for High-Temperature Gas-Cooled Reactor Applications

Bernd A. Thiele, Hermann Diehl, Wilhelm Ohly, Heinz Weber

Nuclear Technology / Volume 66 / Number 3 / September 1984 / Pages 597-606

G. Irradiation Behavior / Status of Metallic Materials Development for Application in Advanced High-Temperature Gas-Cooled Reactor / Material / dx.doi.org/10.13182/NT84-A33481

Irradiation Effects on High-Temperature Gas-Cooled Reactor Structural Materials

James R. Lindgren

Nuclear Technology / Volume 66 / Number 3 / September 1984 / Pages 607-618

G. Irradiation Behavior / Status of Metallic Materials Development for Application in Advanced High-Temperature Gas-Cooled Reactor / Material / dx.doi.org/10.13182/NT84-A33482

Temper and Neutron Irradiation Embrittlement in Cr-1 Mo Steels for Pressure Vessels of High-Temperature Gas-Cooled Reactors

Masahide Suzuki, Kiyoshi Fukaya, Tsuneo Kodaira, Tatsuo Oku

Nuclear Technology / Volume 66 / Number 3 / September 1984 / Pages 619-629

G. Irradiation Behavior / Status of Metallic Materials Development for Application in Advanced High-Temperature Gas-Cooled Reactor / Material / dx.doi.org/10.13182/NT84-A33483

Postirradiation Tensile and Creep Properties of Heat-Resistant Alloys

Nuclear Technology / Volume 66 / Number 3 / September 1984 / Pages 630-638

G. Irradiation Behavior / Status of Metallic Materials Development for Application in Advanced High-Temperature Gas-Cooled Reactor / Material / dx.doi.org/10.13182/NT84-A33484

Influence of Thermal Neutrons on the Brittleness of High-Temperature Gas-Cooled Reactor Liner Steel

A. Alberman, G. Bley, P. Pépin, P. Soulat

Nuclear Technology / Volume 66 / Number 3 / September 1984 / Pages 639-646

G. Irradiation Behavior / Status of Metallic Materials Development for Application in Advanced High-Temperature Gas-Cooled Reactor / Material / dx.doi.org/10.13182/NT84-A33485

Status of Structural Design Code for Metallic High-Temperature Gas-Cooled Reactor Components

Hubertus Nickel, Florian Schubert

Nuclear Technology / Volume 66 / Number 3 / September 1984 / Pages 649-660

H. Design Codes and Life Prediction / Status of Metallic Materials Development for Application in Advanced High-Temperature Gas-Cooled Reactor / Material / dx.doi.org/10.13182/NT84-A33486

High-Temperature Structural Engineering Data Needs

Peter Thomas Hughes, Donald C. Allen

Nuclear Technology / Volume 66 / Number 3 / September 1984 / Pages 661-666

H. Design Codes and Life Prediction / Status of Metallic Materials Development for Application in Advanced High-Temperature Gas-Cooled Reactor / Material / dx.doi.org/10.13182/NT84-A33487

Material Behavior Under Complex Loading

Erik Bodmann, Hans-JüRgen Breuer, Gerhard Raule, Manfred Rödig

Nuclear Technology / Volume 66 / Number 3 / September 1984 / Pages 667-674

H. Design Codes and Life Prediction / Status of Metallic Materials Development for Application in Advanced High-Temperature Gas-Cooled Reactor / Material / dx.doi.org/10.13182/NT84-A33488

Lifetime Test of a Partial Model of a High-Temperature Gas-Cooled Reactor Helium-Helium Heat Exchanger

Masaki Kitagawa, Hiroshi Hattori, Akira Ohtomo, Tetsuo Teramae, Junichi Hamanaka, Hiroshi Ukikusa

Nuclear Technology / Volume 66 / Number 3 / September 1984 / Pages 675-684

H. Design Codes and Life Prediction / Status of Metallic Materials Development for Application in Advanced High-Temperature Gas-Cooled Reactor / Material / dx.doi.org/10.13182/NT84-A33489

Constitutive Equations for the Description of Creep and Creep Rupture Behavior of Metallic Materials at Temperatures Above 800 °C

Heinz-Josef Penkalla, Hans-Helmut Over, Florian Schubert

Nuclear Technology / Volume 66 / Number 3 / September 1984 / Pages 685-692

H. Design Codes and Life Prediction / Status of Metallic Materials Development for Application in Advanced High-Temperature Gas-Cooled Reactor / Material / dx.doi.org/10.13182/NT84-A33490

Methods for Nondestructive Testing of Austenitic High-Temperature Gas-Cooled Reactor Components

Klaus Goebbels, Harald Kapitza

Nuclear Technology / Volume 66 / Number 3 / September 1984 / Pages 695-702

I. Nondestructive Testing / Status of Metallic Materials Development for Application in Advanced High-Temperature Gas-Cooled Reactor / Material / dx.doi.org/10.13182/NT84-A33491