THE FUEL ELEMENT GRAPHITE. Project DRAGON.
Technical Report
·
OSTI ID:4099701
The main requirements of a fuel element graphite for reactors based on the Dragon concept are low transmission coefficient for fission products, dimensional stability under service conditions, high strength, high thermal conductivity, high purity, and high resistance to oxidation. Since conclusions reached in early 1960, a considerable amount of information has accumulated concerning the likely behaviour of graphites in high temperature reactor systems, particularly data on dimensional stability under irradiation. The influence of this new knowledge on the development of fuel element graphite with the Dragon Project is discussed in detail in the final section of this paper.
- Research Organization:
- Atomic Energy Establishment, Winfrith (England)
- NSA Number:
- NSA-24-042192
- OSTI ID:
- 4099701
- Report Number(s):
- DP-Report-146; CONF-630103-13
- Resource Relation:
- Conference: Fuel Element Symposium, Bournemouth, England, 28-29 Jan 1963; Other Information: UNCL. Orig. Receipt Date: 31-DEC-70; Related Information: OECD High Temperature Reactor Project Dragon Report. Now open access.
- Country of Publication:
- United Kingdom
- Language:
- English
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Related Subjects
N30220* -Metals
Ceramics
& Other Materials-Ceramics & Cermets-Preparation & Fabrication
N38100 -Power Reactor Development
DIFFUSION
DRAGON
FISSION PRODUCTS
FUEL ELEMENTS
GASES
GRAPHITE
PRODUCTION
REACTORS
TUBES
GRAPHITE/production of impermeable
for Dragon fuel tubes
methods for
HIGH-TEMPERATURE GAS-COOLED REACTOR EXPERIMENT/fuel tubes for
production of graphite for
Ceramics
& Other Materials-Ceramics & Cermets-Preparation & Fabrication
N38100 -Power Reactor Development
DIFFUSION
DRAGON
FISSION PRODUCTS
FUEL ELEMENTS
GASES
GRAPHITE
PRODUCTION
REACTORS
TUBES
GRAPHITE/production of impermeable
for Dragon fuel tubes
methods for
HIGH-TEMPERATURE GAS-COOLED REACTOR EXPERIMENT/fuel tubes for
production of graphite for