1
Quality control procedures on graphite, pyrocarbon and siliconcarbide : papers presented at the 8th meeting of the Dragon Project Quality Control Working Party, AEE Winfrith, England, 11th and 12th of June, 1974 [E-Book] /
2
Dimensional changes of graphite specimens irradiated in Dragon fuel element 700 . 2 some comments on the irradiation shrinkage of graphite [E-Book]
3
The irradiation of special coated particles designed to test stress model calculated predictions (Dragon met. IV experiment) . 5 post-irradiation examination [E-Book]
4
Graphite behaviour in relation to fuel element design [E-Book]
5
The irradiation behaviour of coated particle fuel compacts [E-Book]
6
Graphite materials data for high temperature nuclear reactors [E-Book]
7
The stress-strain characteristics of non-irradiated and irradiated nuclear graphites [E-Book]
8
Dimensional changes of graphite specimens irradiated in Dragon fuel element 700 [E-Book]
9
Some graphite corrosion problems related to helium cooled high temperature reactors [E-Book]
10
A graphite damage calibration experiment in the Dragon reactor [E-Book]
11
Studies on the behaviour of graphite structures irradiated in the Dragon reactor [E-Book]
12
The role of irradiation experiments in the development of high temperature reactors [E-Book]
13
Measurement of the physical and mechanical properties of pressed gilsocarbon graphite (Dragon ref. 95) [E-Book]
14
Irradiation performance and selection of graphites for HTRS [E-Book]
15
The irradiation behaviour of HTR fuel compacts [E-Book]
16
The thermal and mechanical performance of HTR fuel elements [E-Book]
17
Dragon project metals corrosion programme description of the helium RIG at CIIR Oslo [E-Book]
18
Dimensional and physical property changes of high temperature reactor graphites irradiated at temperature in the range 600 - 1200 centigrade [E-Book]
19
High temperature radiation induced creep in graphite [E-Book]
20
Irradiation performance of HTR fuel compacts [E-Book]