TENTH SEMI-ANNUAL REPORT FOR THE PERIOD JANUARY 1, 1965--JUNE 30, 1965. Project DRAGON.
Technical Report
·
OSTI ID:4093370
- ed.
- Research Organization:
- Atomic Energy Establishment, Winfrith (England)
- NSA Number:
- NSA-24-043694
- OSTI ID:
- 4093370
- Report Number(s):
- DP-Report--390
- Country of Publication:
- United Kingdom
- Language:
- English
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SEMI-ANNUAL REPORT FOR THE PERIOD, JANUARY 1-JUNE 30, 1965
RESEARCH AND DEVELOPMENT DIVISION SECOND SEMI-ANNUAL REPORT FOR PERIOD JANUARY 1 TO JUNE 30, 1961. Project DRAGON.
ELEVENTH SEMI-ANNUAL REPORT FOR THE PERIOD JULY 1, 1965--DECEMBER 31, 1965. Project DRAGON.
Technical Report
·
Wed Sep 22 00:00:00 EDT 1965
·
OSTI ID:4620151
RESEARCH AND DEVELOPMENT DIVISION SECOND SEMI-ANNUAL REPORT FOR PERIOD JANUARY 1 TO JUNE 30, 1961. Project DRAGON.
Technical Report
·
Sun Dec 31 23:00:00 EST 1961
·
OSTI ID:4115528
ELEVENTH SEMI-ANNUAL REPORT FOR THE PERIOD JULY 1, 1965--DECEMBER 31, 1965. Project DRAGON.
Technical Report
·
Fri Dec 31 23:00:00 EST 1965
·
OSTI ID:4085326
Related Subjects
COOLANT LOOPS-- GAS FLOW-- HEAT TRANSFER-- HELIUM
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DRAGON
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chemical and physical
HIGH- TEMPERATURE GAS-COOLED REACTOR EXPERIMENT/physics parameters of
HIGH-TEMPERATURE GAS-COOLED REACTOR EXPERIMENT/coolant for
heat transfer and gas flow properties of helium
HIGH-TEMPERATURE GAS-COOLED REACTOR EXPERIMENT/core components in
corrosion and properties of graphite
HIGH-TEMPERATURE GAS-COOLED REACTOR EXPERIMENT/fuel cycle for
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HIGH-TEMPERATURE GAS-COOLED REACTOR EXPERIMENT/fuel elements for
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HIGH-TEMPERATURE GAS-COOLED REACTOR EXPERIMENT/fuel elements for
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N30220 --Metals
Ceramics
& Other Materials--Ceramics & Cermets--Preparation & Fabrication
N30230 --Metals
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& Other Materials--Ceramics & Cermets--Properties Evaluations
N38100* --Power Reactor Development
POWER REACTORS CARBON-- COATED FUEL PARTICLES-- DESIGN-- DISTRIBUTION- - FISSION PRODUCTS-- FUEL CYCLE-- FUEL ELEMENTS-- FUEL PARTICLES-- FUELS-- PYROLYTIC CARBON-- RADIATION EFFECTS-- TESTING-- THORIUM CARBIDES-- URANIUM CARBIDES
REACTIVITY-- REACTOR CORE-- REACTOR KINETICS
REACTOR FUEL ELEMENTS/ fission product release from pyrolytic carbon coated thorium carbide (ThC$sub 2$)- -uranium carbide (UC$sub 2$) particle
THORIUM CARBIDE
URANIUM CARBIDES/ThC$sub 2$--UC$sub 2$
fission product release from pyrolytic carbon coated particle fuels
(E)
CORROSION-- GRAPHITE-- MECHANICAL PROPERTIES-- RADIATION EFFECTS-- REACTOR CORE
DRAGON
GRAPHITE/properties in gas cooled reactor core components
chemical and physical
HIGH- TEMPERATURE GAS-COOLED REACTOR EXPERIMENT/physics parameters of
HIGH-TEMPERATURE GAS-COOLED REACTOR EXPERIMENT/coolant for
heat transfer and gas flow properties of helium
HIGH-TEMPERATURE GAS-COOLED REACTOR EXPERIMENT/core components in
corrosion and properties of graphite
HIGH-TEMPERATURE GAS-COOLED REACTOR EXPERIMENT/fuel cycle for
analysis of optimum
HIGH-TEMPERATURE GAS-COOLED REACTOR EXPERIMENT/fuel elements for
design parameters of
HIGH-TEMPERATURE GAS-COOLED REACTOR EXPERIMENT/fuel elements for
fission product release from pyrolytic carbon coated thorium carbide (ThC$sub 2$)--uranium carbide (UC$sub 2$) particle
N30220 --Metals
Ceramics
& Other Materials--Ceramics & Cermets--Preparation & Fabrication
N30230 --Metals
Ceramics
& Other Materials--Ceramics & Cermets--Properties Evaluations
N38100* --Power Reactor Development
POWER REACTORS CARBON-- COATED FUEL PARTICLES-- DESIGN-- DISTRIBUTION- - FISSION PRODUCTS-- FUEL CYCLE-- FUEL ELEMENTS-- FUEL PARTICLES-- FUELS-- PYROLYTIC CARBON-- RADIATION EFFECTS-- TESTING-- THORIUM CARBIDES-- URANIUM CARBIDES
REACTIVITY-- REACTOR CORE-- REACTOR KINETICS
REACTOR FUEL ELEMENTS/ fission product release from pyrolytic carbon coated thorium carbide (ThC$sub 2$)- -uranium carbide (UC$sub 2$) particle
THORIUM CARBIDE
URANIUM CARBIDES/ThC$sub 2$--UC$sub 2$
fission product release from pyrolytic carbon coated particle fuels
(E)