MAIN COOLING CIRCUIT OF A HEAVY WATER MODERATED AND COOLED REACTOR WITH PRESTRESSED CONCRETE PRESSURE VESSEL.
Journal Article
·
· pp EN.1/18.1-12 of Symposium on the Technology of Integrated Primary Circuits for Power Reactors, Proceedings, Paris, 20th-22nd May 1968. Paris, European Nuclear Energy Agency, 1968.
OSTI ID:4786110
- Research Organization:
- Siemens Aktiengesellschaft, Erlangen, Ger.
- NSA Number:
- NSA-23-028475
- OSTI ID:
- 4786110
- Journal Information:
- pp EN.1/18.1-12 of Symposium on the Technology of Integrated Primary Circuits for Power Reactors, Proceedings, Paris, 20th-22nd May 1968. Paris, European Nuclear Energy Agency, 1968., Journal Name: pp EN.1/18.1-12 of Symposium on the Technology of Integrated Primary Circuits for Power Reactors, Proceedings, Paris, 20th-22nd May 1968. Paris, European Nuclear Energy Agency, 1968.
- Country of Publication:
- Country unknown/Code not available
- Language:
- English
Similar Records
PRESSURE VESSELS OF PRESTRESSED CONCRETE FOR WATER COOLED REACTORS.
PRESTRESSED CONCRETE PRESSURE VESSELS FOR A 250 Mw(e) HEAVY WATER MODERATED AND CARBON DIOXIDE COOLED REACTOR.
PRESTRESSED CONCRETE PRESSURE VESSELS FOR WATER REACTORS.
Journal Article
·
Wed Oct 30 23:00:00 EST 1968
· pp 273-85 of Development of Light Water Reactors in the Community. Brussels, Euratom, 1967.
·
OSTI ID:4541951
PRESTRESSED CONCRETE PRESSURE VESSELS FOR A 250 Mw(e) HEAVY WATER MODERATED AND CARBON DIOXIDE COOLED REACTOR.
Journal Article
·
Sat Dec 31 23:00:00 EST 1966
· Nucl. Eng. Design, 6: 163-80 (1967).
·
OSTI ID:4504424
PRESTRESSED CONCRETE PRESSURE VESSELS FOR WATER REACTORS.
Journal Article
·
Tue Dec 31 23:00:00 EST 1968
· pp 1329-36 of Pressure Vessel Technology. Pt. II. New York American Society of Mechanical Engineers (1969).
·
OSTI ID:4152796
Related Subjects
CONCRETES
CONFIGURATION
COOLANT LOOPS
DESIGN
FLUID FLOW
HEAVY WATER COOLANT
HEAVY WATER MODERATOR
N38140* --Power Reactor Development--Cooling Systems
POWER PLANTS
PRESSURE VESSELS
PRESTRESSED CONCRETE
REACTOR SAFETY
REACTORS
REACTORS
HEAVY WATER-MODERATED/cooling system for conceptual 600 MW(e)
design parameters for
REACTORS
POWER/cooling system for conceptual 600 MW(e) heavy water cooled and moderated
design parameters for
CONFIGURATION
COOLANT LOOPS
DESIGN
FLUID FLOW
HEAVY WATER COOLANT
HEAVY WATER MODERATOR
N38140* --Power Reactor Development--Cooling Systems
POWER PLANTS
PRESSURE VESSELS
PRESTRESSED CONCRETE
REACTOR SAFETY
REACTORS
REACTORS
HEAVY WATER-MODERATED/cooling system for conceptual 600 MW(e)
design parameters for
REACTORS
POWER/cooling system for conceptual 600 MW(e) heavy water cooled and moderated
design parameters for