1
The development and fabrication of the directly cooled experiment for the Dragon reactor (element 710) [E-Book]

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2
The development and performance of HTR core materials [E-Book]

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3
The development of an overcoating process for fuel cartridge manufacture [E-Book]

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4
The development of an overcoating process for fuel cartridge manufacture [E-Book]

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5
The development of fuel and core materials for high temperature power reactors [E-Book]

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6
The development of low permeability graphite for the Dragon reactor experiment [E-Book]

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

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8
Fuel development for advanced HTR systems [E-Book]

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9
The fuel element graphite [E-Book]

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10
A high temperature graphite irradiation creep experiment in the Dragon reactor [E-Book]
Manzel, R.
1971

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11
High temperature radiation induced creep in graphite [E-Book]

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12
HTR fuel development and testing in the Dragon project [E-Book]

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13
HTR fuel element technology [E-Book]

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14
HTR fuels and their further development [E-Book]

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15
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]

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16
Performance limits of coated particle fuel . 1 the significance of empirical performance diagrams and mathematical models in fuel development and power reactor studies [E-Book]

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17
Performance limits of coated particle fuels [E-Book]

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18
The physical and mechanical properties of Dragon-pechiney G5 graphite [E-Book]
Kamoun, G.
1964

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19
The role of irradiation experiments in the development of high temperature reactors [E-Book]
Barr, P.
1972

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20
Some considerations of steam generators for high temperature gas cooled reactors [E-Book]

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