Fast Reactors and Accelerator Driven Systems Knowledge Base
Conference Article: Reliable core thermal design
Amendola, A. (Commission of the European Communities, Brussels (Belgium))Abstract
The hot spot analysis is no longer limited to the calculation of a simple safety factor against overtemperature, but is now integrated in the overall design philosophy. This paper describes the development of a probabilistic method of analysis and compares it with other advanced calculation methods. Feedbacks from the analysis act:
- on the nominal temperature distribution in order to satisfy the maximum temperature limit and at the same time to optimize the coolant temperature for maximum plant efficiency, and
- on the specifications of manufacturing tolerances and experimental investigations in order to identify and to reduce the most important design uncertainties.
Moreover the computer codes SHOSPA and THEDRA are briefly discussed.
Both codes deliver the zero hot spot probabilitv as a function of the geometrical size assumed for a "spot". THEDRA delivers also the expected hot spot distribution. By means of THEDRA it is possible to evaluate the pins faiIure expectation, if the distribution of pin failures versus operating temperature is known.view the full text of this article (21 pages, format: PDF, size= 1578kB)
key words: heat transfer; hot channel; hot spot factor; hot spots; reactor cores
- Reference:
- Summary report of a panel meeting held in Karlsruhe, 22-24 November 1973 on the recommendation of the International Working Group on Fast Reactors. 1974. p. 133-142
- International Atomic Energy Agency, Vienna (Austria)
- IAEA-TECDOC--166, pp:5-25
- International Atomic Energy Agency, Vienna (Austria)