PROGRAM FOR THE DESIGN AND DEVELOPMENT OF A PLUTONIUM CORE FOR DEMONSTRATION IN A FAST BREEDER REACTOR. Interim Report, September 1, 1967--June 30, 1968.
Technical Report
·
OSTI ID:4794370
- Research Organization:
- Atomic Power Development Associates, Inc., Detroit, Mich.
- NSA Number:
- NSA-23-011234
- OSTI ID:
- 4794370
- Report Number(s):
- APDA-231
- Resource Relation:
- Other Information: UNCL. Orig. Receipt Date: 31-DEC-69
- Country of Publication:
- Country unknown/Code not available
- Language:
- English
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INTERIM REPORT ON PHASE II OF A PROGRAM FOR THE DESIGN AND DEVELOPMENT OF A PLUTONIUM CORE FOR DEMONSTRATION IN A FAST BREEDER REACTOR. [Period Covered], January 1--August 31, 1967.
DEMONSTRATIONS CONDUCTED BY THE PORTABLE CESIUM IRRADIATOR DURING THE PERIOD SEPTEMBER 30, 1967--DECEMBER 19, 1968 AND OPERATION OF THE PORTABLE CESIUM IRRADIATOR REPORT FOR PERIOD AUGUST 11, 1967--JUNE 30, 1969.
DYNAMICS OF A FAST REACTOR WITH IN-CORE THERMIONIC CONVERTERS. Annual Report No. 2, September 1, 1967--August 31, 1968.
Technical Report
·
Fri Oct 31 00:00:00 EST 1969
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OSTI ID:4794370
DEMONSTRATIONS CONDUCTED BY THE PORTABLE CESIUM IRRADIATOR DURING THE PERIOD SEPTEMBER 30, 1967--DECEMBER 19, 1968 AND OPERATION OF THE PORTABLE CESIUM IRRADIATOR REPORT FOR PERIOD AUGUST 11, 1967--JUNE 30, 1969.
Technical Report
·
Wed Jan 01 00:00:00 EST 1969
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OSTI ID:4794370
DYNAMICS OF A FAST REACTOR WITH IN-CORE THERMIONIC CONVERTERS. Annual Report No. 2, September 1, 1967--August 31, 1968.
Technical Report
·
Mon Jan 01 00:00:00 EST 1968
·
OSTI ID:4794370
+2 more
Related Subjects
N38150* -Power Reactor Development-Fuels
DESIGN
FABRICATION
FAST REACTORS
FUELS
LIQUID METAL COOLANT
PLUTONIUM OXIDES
POWER PLANTS
REACTOR CORE
REACTORS
SODIUM
TESTING
URANIUM DIOXIDE
USES
PLUTONIUM OXIDES PuO$sub 2$/PuO$sub 2$-UO$sub 2$
use in demonstration core for fast sodium-cooled reactor
REACTORS
LIQUID METAL- COOLED/core for fast sodium-cooled
design and development of plutonium oxide (PuO$sub 2$)-uranium oxide (UO )
REACTORS
FAST/core for sodium-cooled power
design and development of plutonium oxide (PuO$sub 2$)-uranium oxide (UO )
URANIUM OXIDES UO$sub 2$/PuO$sub 2$-UO$sub 2$
use in demonstration core for fast sodium-cooled reactor
REACTORS
POWER/core for fast sodium-cooled
design and development of plutonium oxide (PuO$sub 2$)-uranium oxide (UO )
DESIGN
FABRICATION
FAST REACTORS
FUELS
LIQUID METAL COOLANT
PLUTONIUM OXIDES
POWER PLANTS
REACTOR CORE
REACTORS
SODIUM
TESTING
URANIUM DIOXIDE
USES
PLUTONIUM OXIDES PuO$sub 2$/PuO$sub 2$-UO$sub 2$
use in demonstration core for fast sodium-cooled reactor
REACTORS
LIQUID METAL- COOLED/core for fast sodium-cooled
design and development of plutonium oxide (PuO$sub 2$)-uranium oxide (UO )
REACTORS
FAST/core for sodium-cooled power
design and development of plutonium oxide (PuO$sub 2$)-uranium oxide (UO )
URANIUM OXIDES UO$sub 2$/PuO$sub 2$-UO$sub 2$
use in demonstration core for fast sodium-cooled reactor
REACTORS
POWER/core for fast sodium-cooled
design and development of plutonium oxide (PuO$sub 2$)-uranium oxide (UO )