Published 1996 | Version v1
Miscellaneous Metadata-only

Creep-fatigue-environment interaction of 9Cr-1Mo-V-Nb steel

Creators

  • 1. Tokyo Univ. (Japan). Dept. of Mechanical Engineering

Description

An extension of the creep-fatigue damage model has been conducted in the present study. The original damage model has been developed to the predict the creep-fatigue life of 9Cr-1Mo-V-Nb steel (Modified 9Cr-1Mo steel) in a very high vacuum environment. The present study is to extend an applicability of the model to the creep-fatigue damage accumulation in the air environment. (orig.)

Part of:
Safety and reliability of plant technology with special emphasis on components of nuclear and conventional power plants - basis for evaluation and operating experience. Vol. 1. Papers 1-30

Additional details

Additional titles

Original title (English)
Sicherheit und Verfuegbarkeit in der Anlagentechnik mit dem Schwerpunkt Komponenten nuklearer und konventioneller Kraftwerke - Beurteilungsgrundlagen und Betriebserfahrungen. Bd. 1. Vortraege 1-30.

Publishing Information

Imprint Title
Safety and reliability of plant technology with special emphasis on components of nuclear and conventional power plants - basis for evaluation and operating experience. Vol. 1. Papers 1-30
Imprint Pagination
574 p.
Journal Page Range
p. 23.-23.13.

Conference

Title
Safety and reliability of plant technology components of nuclear and conventional power plants - basis for evaluation and operating experience.
Original Conference Title
22. MPA-Seminar: Sicherheit und Verfuegbarkeit in der Anlagentechnik -Komponenten nuklearer und konventioneller Kraftwerke - Beuteilungsgrundlagen und Betriebserfahrungen
Acronym
22. MPA seminar
Dates
10-11 Oct 1996.
Place
Stuttgart (Germany).

INIS

Country of Publication
Germany
Country of Input or Organization
Germany
INIS RN
28048604
Subject category
S36: MATERIALS SCIENCE; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
COMPUTER CALCULATIONS; CREEP; FATIGUE; FRACTURE PROPERTIES; S-N DIAGRAM; STEELS; STRAIN RATE; STRESSES
Descriptors DEC
ALLOYS; CARBON ADDITIONS; DIAGRAMS; INFORMATION; IRON ALLOYS; IRON BASE ALLOYS; MECHANICAL PROPERTIES; TRANSITION ELEMENT ALLOYS

Optional Information

Notes
Imprint:Sicherheit und Verfuegbarkeit in der Anlagentechnik mit dem Schwerpunkt Komponenten nuklearer und konventioneller Kraftwerke - Beurteilungsgrundlagen und Betriebserfahrungen. Bd. 1. Vortraege 1-30.