PRESTRESSED CONCRETE REACTOR VESSEL ANALYTICAL METHODS DEVELOPMENT. Final Progress Report, July 1, 1968--June 30, 1969.

Technical Report · Wed Jan 01 00:00:00 EST 1969

DOI:https://doi.org/10.2172/4183897· OSTI ID:4183897

Rashid, Y. R.

• Research Organization: Gulf General Atomic, Inc., San Diego, CA (United States)
• DOE Contract Number: W-7405-ENG-26; SUBCONTRACT NO. 2848
• NSA Number: NSA-24-018790
• OSTI ID: 4183897
• Report Number(s): GA-9488
• Resource Relation: Other Information: For Union Carbide Corp., Nuclear Div., Oak Ridge, Tenn. UNCL. Orig. Receipt Date: 31-DEC-70
• Country of Publication: United States
• Language: English

Related Subjects

N38700* -Reactor Components
Fuels & Accessories
N30330 - Metals
Ceramics
& Other Materials-Plastics & Other Materials-Properties Evaluations
COMPUTERS
CONCRETES
DESIGN
MATHEMATICS
PRESSURE VESSELS
PRESTRESSED CONCRETE
PROGRAMMING
REACTORS
STRESSES
TENSILE PROPERTIES
PRESSURE VESSELS/stress analysis of prestressed concrete
comparison of computer program calculated and model measured
(E/T)
REACTORS/pressure vessels for
development of prestressed concrete
(E/T)
CONCRETES/stress analysis of prestressed
comparison of computer program calculated and model measured
(E/T)
PRESSURE VESSELS/development of prestressed concrete
during July 1968 to June 1969
(E/T)