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The Education, Training & Workforce Development Division provides communication among the academic, industrial, and governmental communities through the exchange of views and information on matters related to education, training and workforce development in nuclear and radiological science, engineering, and technology. Industry leaders, education and training professionals, and interested students work together through Society-sponsored meetings and publications, to enrich their professional development, to educate the general public, and to advance nuclear and radiological science and engineering.
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Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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The American Nuclear Society’s Diversity and Inclusion in ANS (DIA) Committee hosted a workshop social at the 2024 Winter Conference & Expo in November that brought dozens of attendees together for an engaging—and educational—twist on the game show Family Feud.
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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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | doi.org/10.13182/NT84-A33491