1
Carbon deposition studies [E-Book]
2
The correlation of graphite irradiations in the high flux reactor petten and in high temperature reactors [E-Book]
3
Dimensional and physical property changes of high temperature reactor graphites irradiated at temperature in the range 600 - 1200 centigrade [E-Book]
4
Dimensional changes of graphite specimens irradiated in Dragon fuel element 700 [E-Book]
5
Dimensional changes of graphite specimens irradiated in Dragon fuel element 700 . 2 some comments on the irradiation shrinkage of graphite [E-Book]
6
Dragon project metals corrosion programme description of the helium RIG at CIIR Oslo [E-Book]
7
Fast and technical neutron flux measurements in charges III and IV of the Dragon reactor : [E-Book]
8
Graphite and matrix materials for very high temperature reactors [E-Book]
9
Graphite behaviour in relation to fuel element design [E-Book]
10
A graphite damage calibration experiment in the Dragon reactor [E-Book]
11
Graphite materials data for high temperature nuclear reactors [E-Book]
12
Helium impurity levels for compatibility testing of HTR primary circuit materials [E-Book]
13
A high temperature graphite irradiation creep experiment in the Dragon reactor [E-Book]
14
High temperature radiation induced creep in graphite [E-Book]
15
The interpolation of graphite irradiation data for pressed petroleum graphite material reference 152 : [E-Book]
16
The irradiation behaviour of coated particle fuel compacts [E-Book]
17
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]
18
The irradiation behaviour of HTR graphites [E-Book]
19
The irradiation of special coated articles designed to test stress-model calculated predictions : Dragon met. IV experiment . 1 design and specification of experiment [E-Book]
20
The irradiation of special coated particles designed to test stress model calculated predictions (Dragon met. IV experiment) . 5 post-irradiation examination [E-Book]