1
Measurement of the physical and mechanical properties of pressed gilsocarbon graphite (Dragon ref. 95) [E-Book]
Gateau, M.
1969

Full text 
Favorites
Saved in:
2
The correlation of graphite irradiations in the high flux reactor petten and in high temperature reactors [E-Book]

Full text 
Favorites
Saved in:
3
Dimensional changes of graphite specimens irradiated in Dragon fuel element 700 [E-Book]

Full text 
Favorites
Saved in:
4
Some graphite corrosion problems related to helium cooled high temperature reactors [E-Book]

Full text 
Favorites
Saved in:
5
Graphite materials data for high temperature nuclear reactors [E-Book]

Full text 
Favorites
Saved in:
6
The stress-strain characteristics of non-irradiated and irradiated nuclear graphites [E-Book]

Full text 
Favorites
Saved in:
7
Dimensional changes of graphite specimens irradiated in Dragon fuel element 700 . 2 some comments on the irradiation shrinkage of graphite [E-Book]

Full text 
Favorites
Saved in:
8
The kinetics of carbon deposition reactions in high temperature gas cooled reactors [E-Book]

Full text 
Favorites
Saved in:
9
The interpolation of graphite irradiation data for pressed petroleum graphite material reference 152 : [E-Book]

Full text 
Favorites
Saved in:
10
Some aspects of carbon transport in high temperature gas coolded reactors [E-Book]

Full text 
Favorites
Saved in:
11
Carbon deposition studies [E-Book]

Full text 
Favorites
Saved in:
12
A graphite damage calibration experiment in the Dragon reactor [E-Book]

Full text 
Favorites
Saved in:
13
Helium impurity levels for compatibility testing of HTR primary circuit materials [E-Book]

Full text 
Favorites
Saved in:
14
The irradiation behaviour of graphite and matrix materials for HTR use : KFA/Dragon data retrieval programme final status report meeting, 28 - 29 April, 1976 [E-Book]

Full text 
Favorites
Saved in:
15
Irradiation performance and selection of graphites for HTRS [E-Book]

Full text 
Favorites
Saved in:
16
The irradiation behaviour of HTR fuel compacts [E-Book]

Full text 
Favorites
Saved in:
17
Dragon project metals corrosion programme description of the helium RIG at CIIR Oslo [E-Book]

Full text 
Favorites
Saved in:
18
A high temperature graphite irradiation creep experiment in the Dragon reactor [E-Book]
Manzel, R.
1971

Full text 
Favorites
Saved in:
19
The thermal and mechanical performance of HTR fuel elements [E-Book]

Full text 
Favorites
Saved in:
20
Post-irradiation evaluation of Dragon second metallurgical series experiments (FE's 311, 474 and 477) . 1 introduction and irradiation history [E-Book]

Full text 
Favorites
Saved in:

Narrow Search Results