Home / Publications / Journals / Nuclear Technology / Volume 66 / Number 2

Volume 66

Number 2

Table of Contents
Authors(F. Schubert, Udo Bruch, R. Cook, H. Diehl, Philip J. Ennis, W. Jakobeit, H. J. Penkalla, Eberhard te Heesen, G. Ullrich, Kyung Sub Lee, Yuji Kurata, Yutaka Ogawa, Tatsuo Kondo, Tatsuhiko Tanabe, Yoshikazu Sakai, Tatsuo Shikama, Masakazu Fujitsuka, Heitaro Yoshida, Ryoji Watanabe, Tsuneo Nakanishi, Haruo Kawakami, Roger H. Cook, Klaus Schneider, Walter Hartnagel, Peter Schepp, Bernhard Ilschner, Walter Osthoff, Hans Schuster, Philip J. Ennis, Hubertus Nickel, Burkhard Neubauer, Hans-Peter Meurer, Günter K. H. Gnirss, Wolfgang Mergler, Gerhard Raule, Hans Schuster, Georg Ullrich, Peter Soo, Robert L. Sabatini, Hirokazu Tsuji, Tatsuo Kondo, Udo Bruch, Dieter Schuhmacher, Philip J. Ennis, Eberhard te Heesen, Philip J. Ennis, Klaus P. Mohr, Hans Schuster, Klaus Krompholz, Erik Bodmann, Günter K. H. Gnirss, Horst Huthmann, Willem J. Quadakkers, Hans Schuster, H. Inouye, Karl G. E. Brenner, Leslie W. Graham, H. G. A. Bates, Masami Shindo, Tatsuo Kondo, C. C. Li, W. R. Johnson, L. D. Thompson, M. Cappelaere, M. Perrot, J. Sannier)

Creep Rupture Behavior of Candidate Materials for Nuclear Process Heat Applications

F. Schubert, Udo Bruch, R. Cook, H. Diehl, Philip J. Ennis, W. Jakobeit, H. J. Penkalla, Eberhard te Heesen, G. Ullrich

Nuclear Technology / Volume 66 / Number 2 / August 1984 / Pages 227-240

C.2. Creep Property / Status of Metallic Materials Development for Application in Advanced High-Temperature Gas-Cooled Reactor / Material / dx.doi.org/10.13182/NT84-A33426

Creep Rupture Properties of Hastelloy-X and lncoloy-800H in a Simulated HTGR Helium Environment Containing High Levels of Moisture

Kyung Sub Lee

Nuclear Technology / Volume 66 / Number 2 / August 1984 / Pages 241-249

C.2. Creep Property / Status of Metallic Materials Development for Application in Advanced High-Temperature Gas-Cooled Reactor / Material / dx.doi.org/10.13182/NT84-A33427

Creep and Rupture Behavior of a Special Grade Hastelloy-X in Simulated HTGR Helium

Yuji Kurata, Yutaka Ogawa, Tatsuo Kondo

Nuclear Technology / Volume 66 / Number 2 / August 1984 / Pages 250-259

C.2. Creep Property / Status of Metallic Materials Development for Application in Advanced High-Temperature Gas-Cooled Reactor / Material / dx.doi.org/10.13182/NT84-A33428

Creep Rupture Properties of Superalloys Developed for Nuclear Steelmaking

Tatsuhiko Tanabe, Yoshikazu Sakai, Tatsuo Shikama, Masakazu Fujitsuka, Heitaro Yoshida, Ryoji Watanabe

Nuclear Technology / Volume 66 / Number 2 / August 1984 / Pages 260-272

C.2. Creep Property / Status of Metallic Materials Development for Application in Advanced High-Temperature Gas-Cooled Reactor / Material / dx.doi.org/10.13182/NT84-A33429

Creep Properties of Hastelloy-X in Impure Helium Environments

Tsuneo Nakanishi, Haruo Kawakami

Nuclear Technology / Volume 66 / Number 2 / August 1984 / Pages 273-282

C.2. Creep Property / Status of Metallic Materials Development for Application in Advanced High-Temperature Gas-Cooled Reactor / Material / dx.doi.org/10.13182/NT84-A33430

Creep Properties of lnconel-617 in Air and Helium at 800 to 1000°C

Roger H. Cook

Nuclear Technology / Volume 66 / Number 2 / August 1984 / Pages 283-288

C.2. Creep Property / Status of Metallic Materials Development for Application in Advanced High-Temperature Gas-Cooled Reactor / Material / dx.doi.org/10.13182/NT84-A33431

Creep Behavior of Materials for High-Temperature Reactor Application

Klaus Schneider, Walter Hartnagel, Peter Schepp, Bernhard Ilschner

Nuclear Technology / Volume 66 / Number 2 / August 1984 / Pages 289-295

C.2. Creep Property / Status of Metallic Materials Development for Application in Advanced High-Temperature Gas-Cooled Reactor / Material / dx.doi.org/10.13182/NT84-A33432

Creep and Relaxation Behavior of lnconel-617

Walter Osthoff, Hans Schuster, Philip J. Ennis, Hubertus Nickel

Nuclear Technology / Volume 66 / Number 2 / August 1984 / Pages 296-307

C.2. Creep Property / Status of Metallic Materials Development for Application in Advanced High-Temperature Gas-Cooled Reactor / Material / dx.doi.org/10.13182/NT84-A33433

Remaining-Life Estimation for High-Temperature Materials Under Creep Load by Replicas

Burkhard Neubauer

Nuclear Technology / Volume 66 / Number 2 / August 1984 / Pages 308-312

C.2. Creep Property / Status of Metallic Materials Development for Application in Advanced High-Temperature Gas-Cooled Reactor / Material / dx.doi.org/10.13182/NT84-A33434

Investigations on the Fatigue Behavior of High-Temperature Alloys for High-Temperature Gas-Cooled Reactor Components

Hans-Peter Meurer, Gunter K. H. Gnirss, Wolfgang Mergler, Gerhard Raule, Hans Schuster, Georg Ullrich

Nuclear Technology / Volume 66 / Number 2 / August 1984 / Pages 315-323

C.3. Fatigue Property / Status of Metallic Materials Development for Application in Advanced High-Temperature Gas-Cooled Reactor / Material / dx.doi.org/10.13182/NT84-A33435

High-Cycle Fatigue Behavior of Incoloy Alloy 800H in a Simulated HTGR Helium Environment Containing High Moisture Levels

Peter Soo, Robert L. Sabatini

Nuclear Technology / Volume 66 / Number 2 / August 1984 / Pages 324-346

C.3. Fatigue Property / Status of Metallic Materials Development for Application in Advanced High-Temperature Gas-Cooled Reactor / Material / dx.doi.org/10.13182/NT84-A33436

Low-Cycle Fatigue of Heat-Resistant Alloys in High-Temperature Gas-Cooled Reactor Helium

Hirokazu Tsuji, Tatsuo Kondo

Nuclear Technology / Volume 66 / Number 2 / August 1984 / Pages 347-353

C.3. Fatigue Property / Status of Metallic Materials Development for Application in Advanced High-Temperature Gas-Cooled Reactor / Material / dx.doi.org/10.13182/NT84-A33437

Tensile and Impact Properties of Candidate Alloys for High-Temperature Gas-Cooled Reactor Applications

Udo Bruch, Dieter Schuhmacher, Philip J. Ennis, Eberhard te Heesen

Nuclear Technology / Volume 66 / Number 2 / August 1984 / Pages 357-362

C.4. Short-Term Property / Status of Metallic Materials Development for Application in Advanced High-Temperature Gas-Cooled Reactor / Material / dx.doi.org/10.13182/NT84-A33438

Effect of Carburizing Service Environments on the Mechanical Properties of High-Temperature Alloys

Philip J. Ennis, Klaus P. Mohr, Hans Schuster

Nuclear Technology / Volume 66 / Number 2 / August 1984 / Pages 363-368

C.4. Short-Term Property / Status of Metallic Materials Development for Application in Advanced High-Temperature Gas-Cooled Reactor / Material / dx.doi.org/10.13182/NT84-A33439

Fracture Mechanics Investigations on High-Temperature Gas-Cooled Reactor Materials

Klaus Krompholz, Erik Bodmann, Günter K. H. Gnirss, Horst Huthmann

Nuclear Technology / Volume 66 / Number 2 / August 1984 / Pages 371-379

C.5. Fracture Mechanic / Status of Metallic Materials Development for Application in Advanced High-Temperature Gas-Cooled Reactor / Material / dx.doi.org/10.13182/NT84-A33440

Thermodynamic and Kinetic Aspects of the Corrosion of High-Temperature Alloys in High-Temperature Gas-Cooled Reactor Helium

Willem J. Quadakkers, Hans Schuster

Nuclear Technology / Volume 66 / Number 2 / August 1984 / Pages 383-391

D.Gas/Metal Reaction / Status of Metallic Materials Development for Application in Advanced High-Temperature Gas-Cooled Reactor / Material / dx.doi.org/10.13182/NT84-A33441

Relationship of H₂O and CH4 Supply Rates in HTGR Helium to the Carburization of Hastelloy-X and Alloy 800H

H. Inouye

Nuclear Technology / Volume 66 / Number 2 / August 1984 / Pages 392-403

D.Gas/Metal Reaction / Status of Metallic Materials Development for Application in Advanced High-Temperature Gas-Cooled Reactor / Material / dx.doi.org/10.13182/NT84-A33442

The Development and Application of a Unified Corrosion Model for High-Temperature Gas-Cooled Reactor Systems

Karl G. E. Brenner, Leslie W. Graham

Nuclear Technology / Volume 66 / Number 2 / August 1984 / Pages 404-414

D.Gas/Metal Reaction / Status of Metallic Materials Development for Application in Advanced High-Temperature Gas-Cooled Reactor / Material / dx.doi.org/10.13182/NT84-A33443

The Corrosion Behavior of High-Temperature Alloys During Exposure for Times up to 10 000 h in Prototype Nuclear Process Helium at 700 to 900°C

H. G. A. Bates

Nuclear Technology / Volume 66 / Number 2 / August 1984 / Pages 415-428

D.Gas/Metal Reaction / Status of Metallic Materials Development for Application in Advanced High-Temperature Gas-Cooled Reactor / Material / dx.doi.org/10.13182/NT84-A33444

Evaporation Behavior of Hastelloy-X Alloys in Simulated Very High Temperature Reactor Environments

Masami Shindo, Tatsuo Kondo

Nuclear Technology / Volume 66 / Number 2 / August 1984 / Pages 429-438

D.Gas/Metal Reaction / Status of Metallic Materials Development for Application in Advanced High-Temperature Gas-Cooled Reactor / Material / dx.doi.org/10.13182/NT84-A33445

The Effects of Controlled Impurity Helium on the Mechanical Behavior of Hastelloy Alloy X

C. C. Li, W. R. Johnson, L. D. Thompson

Nuclear Technology / Volume 66 / Number 2 / August 1984 / Pages 439-464

D.Gas/Metal Reaction / Status of Metallic Materials Development for Application in Advanced High-Temperature Gas-Cooled Reactor / Material / dx.doi.org/10.13182/NT84-A33446

Behavior of Metallic Materials Between 550 and 870°C in High-Temperature Gas-Cooled Reactor Helium Under Pressures of 2 and 50 bar

M. Cappelaere, M. Perrot, J. Sannier

Nuclear Technology / Volume 66 / Number 2 / August 1984 / Pages 465-478

D.Gas/Metal Reaction / Status of Metallic Materials Development for Application in Advanced High-Temperature Gas-Cooled Reactor / Material / dx.doi.org/10.13182/NT84-A33447