ANS / Publications / Journals / Nuclear Technology

Manufacture of a Heat-Resistant Alloy with Modified Specifications for HTGR Structural Applications

Kensho Sahira, Toshiki Takeiri, Tatsuo Kondo

Nuclear Technology / Volume 66 / Number 1 / July 1984 / Pages 25-34

A. Selection, Production, and Development of Alloys for HTGR Component / Status of Metallic Materials Development for Application in Advanced High-Temperature Gas-Cooled Reactor / Material / dx.doi.org/10.13182/NT84-A33451

Production and Welding Technology of Some High-Temperature Nickel Alloys in Relation to Their Properties

T. H. Bassford, James C. Hosier

Nuclear Technology / Volume 66 / Number 1 / July 1984 / Pages 35-43

A. Selection, Production, and Development of Alloys for HTGR Component / Status of Metallic Materials Development for Application in Advanced High-Temperature Gas-Cooled Reactor / Material / dx.doi.org/10.13182/NT84-A33452

Weldability and Weld Performance of a Special Grade Hastelloy-X Modified for High-Temperature Gas-Cooled Reactors

Shigeki Shimizu, Yasushi Mutoh

Nuclear Technology / Volume 66 / Number 1 / July 1984 / Pages 44-53

A. Selection, Production, and Development of Alloys for HTGR Component / Status of Metallic Materials Development for Application in Advanced High-Temperature Gas-Cooled Reactor / Material / dx.doi.org/10.13182/NT84-A33453

Hot Extruded High-Temperature Alloy Tubes and Some Mechanical Properties

Herbert Aigner, H. Peter Degischer, Erich Hertner

Nuclear Technology / Volume 66 / Number 1 / July 1984 / Pages 54-62

A. Selection, Production, and Development of Alloys for HTGR Component / Status of Metallic Materials Development for Application in Advanced High-Temperature Gas-Cooled Reactor / Material / dx.doi.org/10.13182/NT84-A33454

lnconel-618E: An Alloy Developed for High-Temperature Gas-Cooled Reactor Service

A. C. Lingenfelter

Nuclear Technology / Volume 66 / Number 1 / July 1984 / Pages 63-68

A. Selection, Production, and Development of Alloys for HTGR Component / Status of Metallic Materials Development for Application in Advanced High-Temperature Gas-Cooled Reactor / Material / dx.doi.org/10.13182/NT84-A33455

Grain Boundary Precipitation Treatment for Improving the High-Temperature Low-Cycle Fatigue Strength of SSS113M for VHTRs

Rikizo Watanabe

Nuclear Technology / Volume 66 / Number 1 / July 1984 / Pages 69-74

A. Selection, Production, and Development of Alloys for HTGR Component / Status of Metallic Materials Development for Application in Advanced High-Temperature Gas-Cooled Reactor / Material / dx.doi.org/10.13182/NT84-A33456

Research and Development on Heat-Resistant Alloys for Nuclear Process Heating in Japan

Ryohei Tanaka, Tatsuo Kondo

Nuclear Technology / Volume 66 / Number 1 / July 1984 / Pages 75-87

A. Selection, Production, and Development of Alloys for HTGR Component / Status of Metallic Materials Development for Application in Advanced High-Temperature Gas-Cooled Reactor / Material / dx.doi.org/10.13182/NT84-A33457

Design of Wrought Nickel-Base Alloys for Advanced High-Temperature Gas-Cooled Reactor Applications

W. R. Johnson, L. D. Thompson, Thomas A. Lechtenberg

Nuclear Technology / Volume 66 / Number 1 / July 1984 / Pages 88-101

A. Selection, Production, and Development of Alloys for HTGR Component / Status of Metallic Materials Development for Application in Advanced High-Temperature Gas-Cooled Reactor / Material / dx.doi.org/10.13182/NT84-A33458

Experimental Work on Alloy Development for High-Temperature Gas-Cooled Reactor Systems

M. R. Warren

Nuclear Technology / Volume 66 / Number 1 / July 1984 / Pages 102-116

A. Selection, Production, and Development of Alloys for HTGR Component / Status of Metallic Materials Development for Application in Advanced High-Temperature Gas-Cooled Reactor / Material / dx.doi.org/10.13182/NT84-A33459

The Development of High-Strength Alloys Resistant to Corrosion in Impure Helium

A. V. Dean, Philip J. Ennis

Nuclear Technology / Volume 66 / Number 1 / July 1984 / Pages 117-123

A. Selection, Production, and Development of Alloys for HTGR Component / Status of Metallic Materials Development for Application in Advanced High-Temperature Gas-Cooled Reactor / Material / dx.doi.org/10.13182/NT84-A33460

Phase Analysis of High-Temperature Alloys for Nuclear Application by Interference Layer Metallography

Helmut Hoven, Karl Koizlik, Hubertus Nickel

Nuclear Technology / Volume 66 / Number 1 / July 1984 / Pages 127-138

B. Structural Characterization of Microstructure and Matallographical Aspect / Status of Metallic Materials Development for Application in Advanced High-Temperature Gas-Cooled Reactor / Material / dx.doi.org/10.13182/NT84-A33461

Precipitation Behavior of Ni-Cr-22 Fe-18 Mo (Hastelloy-X) and Ni-Cr-22 Co-12 Mo (Inconel-617) After Isothermal Aging

Hermann Kirchhöfer, Florian Schubert, Hubertus Nickel

Nuclear Technology / Volume 66 / Number 1 / July 1984 / Pages 139-148

B. Structural Characterization of Microstructure and Matallographical Aspect / Status of Metallic Materials Development for Application in Advanced High-Temperature Gas-Cooled Reactor / Material / dx.doi.org/10.13182/NT84-A33462

Impact Strength and Transmission Electron Microscopy Investigations of Aged and Carburized Alloy 800H

Aleksandra Czyrska-Filemonowicz, Philip J. Ennis

Nuclear Technology / Volume 66 / Number 1 / July 1984 / Pages 149-157

B. Structural Characterization of Microstructure and Matallographical Aspect / Status of Metallic Materials Development for Application in Advanced High-Temperature Gas-Cooled Reactor / Material / dx.doi.org/10.13182/NT84-A33463

Hastelloy-X for High Temperature Gas-Cooled Reactor Applications

H. E. McCoy, J. P. Strizak, J. F. King

Nuclear Technology / Volume 66 / Number 1 / July 1984 / Pages 161-174

C. 1. Mechanical Property / Status of Metallic Materials Development for Application in Advanced High-Temperature Gas-Cooled Reactor / Material / dx.doi.org/10.13182/NT84-A33464

Mechanical Properties of Heat-Resistant Alloys Exposed to Air and HTGR Helium at High Temperatures

Junzo Fujioka, Norio Fukasako, Hirokazu Murase, Yukio Nishiyama

Nuclear Technology / Volume 66 / Number 1 / July 1984 / Pages 175-185

C. 1. Mechanical Property / Status of Metallic Materials Development for Application in Advanced High-Temperature Gas-Cooled Reactor / Material / dx.doi.org/10.13182/NT84-A33465

Mechanical Characterization of Metallic Materials for High-Temperature Gas-Cooled Reactors in Air and in Helium Environments

G. Sainfort, J. Sannier, M. Cappelaere, J. Grégoire

Nuclear Technology / Volume 66 / Number 1 / July 1984 / Pages 186-194

C. 1. Mechanical Property / Status of Metallic Materials Development for Application in Advanced High-Temperature Gas-Cooled Reactor / Material / dx.doi.org/10.13182/NT84-A33466

Evaluation of High-Temperature Alloys for Helium Gas Turbines

Wolfgang Jakobeit, Jörn-Peter Pfeifer, Georg Ullrich

Nuclear Technology / Volume 66 / Number 1 / July 1984 / Pages 195-206

C. 1. Mechanical Property / Status of Metallic Materials Development for Application in Advanced High-Temperature Gas-Cooled Reactor / Material / dx.doi.org/10.13182/NT84-A33467

Mechanical Properties of Welds in Commercial Alloys for High-Temperature Gas-Cooled Reactor Components

James R. Lindgren, Brian E. Thurgood, Robin H. Ryder, Chia-Chuan Li

Nuclear Technology / Volume 66 / Number 1 / July 1984 / Pages 207-213

C. 1. Mechanical Property / Status of Metallic Materials Development for Application in Advanced High-Temperature Gas-Cooled Reactor / Material / dx.doi.org/10.13182/NT84-A33468

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

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