RESEARCH AND DEVELOPMENT DIVISION FIRST SEMI-ANNUAL REPORT FOR PERIOD JULY 1, 1960 TO DECEMBER 31, 1960. Project DRAGON.
Technical Report
·
OSTI ID:4136563
- ed.
- Research Organization:
- Atomic Energy Establishment, Winfrith (England)
- NSA Number:
- NSA-24-040891
- OSTI ID:
- 4136563
- Report Number(s):
- NP--10477; DP-Report--34
- Country of Publication:
- Country unknown/Code not available
- Language:
- English
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Related Subjects
COATED FUEL PARTICLES
COOLANT LOOPS
CORROSION
DRAGON
FABRICATION
FISSION PRODUCTS
FUEL ELEMENTS
GAS COOLANT
GAS FLOW
GRAPHITE
GRAPHITE/properties in gas cooled reactor core components
chemical and physical
HEAT TRANSFER
HELIUM
HIGH- TEMPERATURE GAS-COOLED REACTOR EXPERIMENT/fuels for
preparation and properties of coated particle
HIGH-TEMPERATURE GAS- C
HIGH-TEMPERATURE GAS-COOLED REACTOR EXPERIMENT/ fuel elements for
fission product release from
HIGH-TEMPERATURE GAS-COOLED REACTOR EXPERIMENT/ materials development for
HIGH-TEMPERATURE GAS-COOLED REACTOR EXPERIMENT/coolant for
heat transfer and gas flow properties of helium
(E)
HIGH-TEMPERATURE GAS-COOLED REACTOR EXPERIMENT/coolant for
purification system for helium
HIGH-TEMPERATURE GAS-COOLED REACTOR EXPERIMENT/cooling system of
heat transfer characteristics of
(E)
HIGH-TEMPERATURE GAS-COOLED REACTOR EXPERIMENT/instrument development for
HIGH-TEMPERATURE GAS-COOLED REACTOR EXPERIMENT/physics parameters for
IMPURITIES
INSTRUMENTS
IRRADIATION
LOSSES
MECHANICAL PROPERTIES
N30220 --Metals
Ceramics
& Other Materials--Ceramics & Cermets--Preparation & Fabrication
N30230 --Metals
Ceramics
& Other Materials--Ceramics & Cermets--Properties Evaluations
N38100* --Power Reactor Development
PREPARATION
PRODUCTION
RADIATION EFFECTS
REACTOR CORE
REACTOR KINETICS
REACTORS
TESTING
THORIUM CARBIDES
THORIUM CARBIDES/ThC$sub 2$--UC$sub 2$
production of coated particle fuels of
URANIUM CARBIDES
URANIUM CARBIDES/ThC$sub 2$--UC$sub 2$
production of coated particle fuels of
COOLANT LOOPS
CORROSION
DRAGON
FABRICATION
FISSION PRODUCTS
FUEL ELEMENTS
GAS COOLANT
GAS FLOW
GRAPHITE
GRAPHITE/properties in gas cooled reactor core components
chemical and physical
HEAT TRANSFER
HELIUM
HIGH- TEMPERATURE GAS-COOLED REACTOR EXPERIMENT/fuels for
preparation and properties of coated particle
HIGH-TEMPERATURE GAS- C
HIGH-TEMPERATURE GAS-COOLED REACTOR EXPERIMENT/ fuel elements for
fission product release from
HIGH-TEMPERATURE GAS-COOLED REACTOR EXPERIMENT/ materials development for
HIGH-TEMPERATURE GAS-COOLED REACTOR EXPERIMENT/coolant for
heat transfer and gas flow properties of helium
(E)
HIGH-TEMPERATURE GAS-COOLED REACTOR EXPERIMENT/coolant for
purification system for helium
HIGH-TEMPERATURE GAS-COOLED REACTOR EXPERIMENT/cooling system of
heat transfer characteristics of
(E)
HIGH-TEMPERATURE GAS-COOLED REACTOR EXPERIMENT/instrument development for
HIGH-TEMPERATURE GAS-COOLED REACTOR EXPERIMENT/physics parameters for
IMPURITIES
INSTRUMENTS
IRRADIATION
LOSSES
MECHANICAL PROPERTIES
N30220 --Metals
Ceramics
& Other Materials--Ceramics & Cermets--Preparation & Fabrication
N30230 --Metals
Ceramics
& Other Materials--Ceramics & Cermets--Properties Evaluations
N38100* --Power Reactor Development
PREPARATION
PRODUCTION
RADIATION EFFECTS
REACTOR CORE
REACTOR KINETICS
REACTORS
TESTING
THORIUM CARBIDES
THORIUM CARBIDES/ThC$sub 2$--UC$sub 2$
production of coated particle fuels of
URANIUM CARBIDES
URANIUM CARBIDES/ThC$sub 2$--UC$sub 2$
production of coated particle fuels of