THEORY AND PRACTICE OF DETERMINING LEAK RATES OF REACTOR SAFETY CONTAINMENTS. PART II (in German)
Journal Article
·
· Atomwirtschaft (West Germany) Changed to ATW, Atomwirtsch., Atomtech.
OSTI ID:4049302
A measuring process was developed for determining leak rates in reactor containment vessels in which a metal wire is used as a resistance thermometer. Because of the difficulties accompanying the use of a free, stretched wire in a large container, a hemp rope was used as a carrier for the wire which was laid between the strands. The theory and practice of this process are described in terms of the practical example provided by the tightness testing of the reactor chamber of the DIDO reactor (FRJ-2) in the Julich Nuc1ear Research Centre. The method had the expected advantages in addition to an improvement in the accuracy of measurement. It proved possible to construct the measuring arrangement and mount the cable in about three hours. The investigation described occupied only 2 to 3 workers for 24 hours and, compared with similar tightness tests on reactor chambers performed using other arrangements, led to a considerable lowering of costs. After the experiment the calibration of the cable was again checked without any change of resistance or of temperature coefficient being detectable within the limits of measurement. (auth)
- Research Organization:
- Originating Research Org. not identified
- NSA Number:
- NSA-18-019282
- OSTI ID:
- 4049302
- Journal Information:
- Atomwirtschaft (West Germany) Changed to ATW, Atomwirtsch., Atomtech., Journal Name: Atomwirtschaft (West Germany) Changed to ATW, Atomwirtsch., Atomtech. Vol. Vol: 9; ISSN ATWSA
- Country of Publication:
- Country unknown/Code not available
- Language:
- German
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