Review of areas that may require simultaneous coupled solution of the thermal hydraulic and fission product/aerosol behavior equations for source term determination. [PWR; BWR].

Author: Kress, T. S.
Published: United States : [publisher not identified], 1984
Springfield, Va.: National Technical Information Service, [approximately 1984]
Physical Description: microfiche : negative ; 11 x 15 cm

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Summary

In the determination of the behavior of nuclear aerosols in the reactor coolant system and in the containment for the development of severe accident source terms, present practice generally is to first perform thermal hydraulic calculations for specific plant types and sequences and then to utilize the results as input for separate fission product/aerosol dynamic transport calculations. It is recognized that there are several areas in which the thermal-hydraulics and the fission product/aerosol behavior may be significantly coupled and that it is then basically incorrect to do the analyses in a separated manner. This review paper produces a speculative list of these potentially coupled areas and attempts to assess the importance of the coupling for as many of the specific items that time has allowed before this conference.

Report Numbers

DE85001106; CONF-8409112-3

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NTIS collection.

Note

DOE contract number: AC05-84OR21400
OSTI Identifier 6776571
Research organization: Oak Ridge National Lab., TN (USA).

View MARC record | catkey: 47346604

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Review of areas that may require simultaneous coupled solution of the thermal hydraulic and fission product/aerosol behavior equations for source term determination. [PWR; BWR].

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