TESTS AND RESEARCHES CONCERNED WITH STRUCTURAL DESIGN CRITERIA FOR PRIMARY COOLANT PIPING SYSTEM OF NUCLEAR REACTOR. 2. STRAIN-CONTROLLED LOW-CYCLE FATIGUE STRENGTH OF SMALL SPECIMENS. (in Japanese)
Journal Article
·
· Yosetsu Gijutsu 18: No. 7, 135-46(Jul 1970).
OSTI ID:4054864
- Research Organization:
- Originating Research Org. not identified
- NSA Number:
- NSA-25-018255
- OSTI ID:
- 4054864
- Journal Information:
- Yosetsu Gijutsu 18: No. 7, 135-46(Jul 1970)., Other Information: Orig. Receipt Date: 31-DEC-71; Bib. Info. Source: JA (JA)
- Country of Publication:
- Japan
- Language:
- Japanese
Similar Records
TESTS AND RESEARCHES CONCERNED WITH STRUCTURAL DESIGN CRITERIA FOR PRIMARY COOLANT PIPING SYSTEM OF NUCLEAR REACTOR. 2. STRAIN-CONTROLLED LOW-CYCLE FATIGUE STRENGTH OF SMALL SPECIMENS.
TESTS AND RESEARCHES CONCERNED WITH STRUCTURAL DESIGN CRITERIA FOR PRIMARY COOLANT PIPING SYSTEM OF NUCLEAR REACTOR. 2. STRAIN-CONTROLLED LOW-CYCLE FATIGUE STRENGTH OF SMALL SPECIMENS.
TEST CONCERNING THE STRUCTURAL DESIGN CRITERIA FOR THE PRIMARY COOLANT PIPING OF A NUCLEAR REACTOR.
Journal Article
·
Thu Jan 01 00:00:00 EST 1970
· Yosetsu Gijutsu 18: No. 5, 125-34(May 1970).
·
OSTI ID:4054864
TESTS AND RESEARCHES CONCERNED WITH STRUCTURAL DESIGN CRITERIA FOR PRIMARY COOLANT PIPING SYSTEM OF NUCLEAR REACTOR. 2. STRAIN-CONTROLLED LOW-CYCLE FATIGUE STRENGTH OF SMALL SPECIMENS.
Journal Article
·
Thu Jan 01 00:00:00 EST 1970
· Yosetsu Gijutsu 18: No. 8, 145-52(Aug 1970).
·
OSTI ID:4054864
TEST CONCERNING THE STRUCTURAL DESIGN CRITERIA FOR THE PRIMARY COOLANT PIPING OF A NUCLEAR REACTOR.
Journal Article
·
Thu Jan 01 00:00:00 EST 1970
· Yosetsu Gijutsu 18: No. 4, 148-50(Apr 1970).
·
OSTI ID:4054864
Related Subjects
N38700* -Reactor Components
Fuels & Accessories
COOLANT LOOPS
DESIGN
DUCTILITY
MECHANICAL PROPERTIES
PIPES
REACTORS
STRAIN
TENSILE PROPERTIES
TESTING
PIPES/mechanical properties of reactor primary cooling system
design requirements for
REACTORS/cooling system for
structural design requirements for piping of primary
Fuels & Accessories
COOLANT LOOPS
DESIGN
DUCTILITY
MECHANICAL PROPERTIES
PIPES
REACTORS
STRAIN
TENSILE PROPERTIES
TESTING
PIPES/mechanical properties of reactor primary cooling system
design requirements for
REACTORS/cooling system for
structural design requirements for piping of primary