Fast Reactors and Accelerator Driven Systems Knowledge Base

Conference Article: Part 1 and 2 of CNEN activities on the thermal desing of fast reactor fuel elements (status report)

Amelotti, F.; Barbaro, M.; Spagna, F.; Iannuzzo, P.; Falzetti, L.; Martini, M

Abstract

This report reviews the CNEN activities on the thermal design of fast reactor fuel elements, carried out in the framework of the Italian Fast Reactor Program (PRV). The first part of the report deals with the status of the thermal design of the PEC fast reactor core and with the experience gained at PRV upon some hot channel analysis methods. Hot channel calculations for the EPEC-4 (U02 fueled) core concept are presented. The results of two methods for the combination of the uncertainties (semistatistical and SHOSPA) are compared. Guidelines for thermal analysis of a mixed oxide core concept (EPEC-5), now under investigation, are discussed. The second part deals with the status of the experimental program in support of the thermal design, carried out at USTS, Casaccia. The principal features of the panned sodium thermohydraulic and thermomechanical tests on highly instrumented fuel element partial mock-ups (unheated and heated rod bundles) are reviewed. Preliminary results, mainly concerned with test section design, characterization and instrumentation, are presented.

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key words: fast reactors; fuel elements; heat transfer; hot channel factor; pec brasimone reactor; reactor cores; specifications
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:134-162