Quality Control Procedures for HTGR Fuel Element Components
Quality Control Procedures for HTGR Fuel Element Components
The growing use of nuclear reactors for the production of electric power throughout the world, and the consequent increase in the number of nuclear fuel manufacturers, is giving enhanced importance to the consideration of quality assurance in the production of nuclear fuels. The fuel is the place, w...
Saved in:
Personal Name(s): | Delle, W. W. |
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Koizlik, K. / Luhleich, H. / Nickel, Hubertus | |
Contributing Institute: |
Publikationen vor 2000; PRE-2000; Retrocat |
Imprint: |
Jülich
Kernforschungsanlage Jülich, Verlag
1976
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Physical Description: |
37 p. |
Document Type: |
Report Book |
Research Program: |
ohne Topic |
Series Title: |
Berichte der Kernforschungsanlage Jülich
1333 |
Link: |
OpenAccess OpenAccess |
Publikationsportal JuSER |
The growing use of nuclear reactors for the production of electric power throughout the world, and the consequent increase in the number of nuclear fuel manufacturers, is giving enhanced importance to the consideration of quality assurance in the production of nuclear fuels. The fuel is the place, where the radioactive fission products are produced in the reactor and, therefore, the integrity of the fuel is of utmost importance. The first and most fundamental means of insuring that integrity is through the exercise of properly designed quality assurance programmes during the manufacture of the fuel and other fuel element components. The International Atomic Energy Agency therefore conducted an International Seminar on Nuclear Fuel Quality Assurance in Oslo, Norway from 24 till 28 May, 1976. The seminar was addressed to a wider audience and was, with its educational content, of interest in those countries newly entering the field as well as in those with established nuclear fuel fabrication capabilities. This KFA report contains a paper which was distributed preliminary during the seminar'and - in the second part - the text of the oral presentation. The tables and figures were presented as slides. The paper gives a summary of the procedures available in the present state for the production control of HTGR core materials and of the meaning of the particular properties for reactor operation. The work was partly sponsored by the Bundesministerium für Forschung und Technologie of the Federal Republic of Germany as well as by the Government of North-Rhine-Westfalia. |