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Abstract

In the event of a hypothetical severe accident in a sodium cooled fast breeder reactor, molten core material may interact with liquid sodium. A rapid quenching may result in the formation of debris that settles on horizontal surfaces within the reactor vessel, forming debris beds. The beds are heated by the radioactive decay of retained fission products. The safety concern attached to these severe post-accident scenarios depends upon the extent to which natural cooling of the debris may be relied upon to remove decay heat from the bed. A joint program to study the coolability of the self heated debris beds has been performed under the sponsorship of the USNRC, the JRC of the European Communities and PNC Japan. The program, conducted at Sandia National Laboratories is being completed in 1985. This paper provides a review of the program's twelve experiments and the data obtained from those experiments. The test series was performed to provide data which could be used to develop experimentally validated models for the coolability of self heated debris beds. The experiments showed that the debris may be coolable but maximum temperatures in the order of the melting point of some core materials should be expected.

Additional information

Authors: MITCHELL G W, SANDIA NATIONAL LABORATORY, ALBUQUERQUE (USA);JRC ISPRA ESTAB. (ITALY), POWER REACTOR AND NUCLEAR FUEL DEVELOPMENT CORP (JAPAN);KERNFORSCHUNGSZENTRUM KARLSRUHE (GERMANY);CENTRE D'ETUDES NUCLEAIR;RIVARD J B, SANDIA NATIONAL LABORATORY, ALBUQUERQUE (USA);JRC ISPRA ESTAB. (ITALY), POWER REACTOR AND NUCLEAR FUEL DEVELOPMENT CORP (JAPAN);KERNFORSCHUNGSZENTRUM KARLSRUHE (GERMANY);CENTRE D'ETUDES NUCLEAIR;HITCHCOCK J T, SANDIA NATIONAL LABORATORY, ALBUQUERQUE (USA);JRC ISPRA ESTAB. (ITALY), POWER REACTOR AND NUCLEAR FUEL DEVELOPMENT CORP (JAPAN);KERNFORSCHUNGSZENTRUM KARLSRUHE (GERMANY);CENTRE D'ETUDES NUCLEAIR;MEISTER H, SANDIA NATIONAL LABORATORY, ALBUQUERQUE (USA);JRC ISPRA ESTAB. (ITALY), POWER REACTOR AND NUCLEAR FUEL DEVELOPMENT CORP (JAPAN);KERNFORSCHUNGSZENTRUM KARLSRUHE (GERMANY);CENTRE D'ETUDES NUCLEAIR;MEHR K, SANDIA NATIONAL LABORATORY, ALBUQUERQUE (USA);JRC ISPRA ESTAB. (ITALY), POWER REACTOR AND NUCLEAR FUEL DEVELOPMENT CORP (JAPAN);KERNFORSCHUNGSZENTRUM KARLSRUHE (GERMANY);CENTRE D'ETUDES NUCLEAIR;TAKAHASHI K, SANDIA NATIONAL LABORATORY, ALBUQUERQUE (USA);JRC ISPRA ESTAB. (ITALY), POWER REACTOR AND NUCLEAR FUEL DEVELOPMENT CORP (JAPAN);KERNFORSCHUNGSZENTRUM KARLSRUHE (GERMANY);CENTRE D'ETUDES NUCLEAIR;NAKAMURA H, SANDIA NATIONAL LABORATORY, ALBUQUERQUE (USA);JRC ISPRA ESTAB. (ITALY), POWER REACTOR AND NUCLEAR FUEL DEVELOPMENT CORP (JAPAN);KERNFORSCHUNGSZENTRUM KARLSRUHE (GERMANY);CENTRE D'ETUDES NUCLEAIR;FIEG G, SANDIA NATIONAL LABORATORY, ALBUQUERQUE (USA);JRC ISPRA ESTAB. (ITALY), POWER REACTOR AND NUCLEAR FUEL DEVELOPMENT CORP (JAPAN);KERNFORSCHUNGSZENTRUM KARLSRUHE (GERMANY);CENTRE D'ETUDES NUCLEAIR;SCHWARZ M SANDIA NATIONAL LABORATORY, ALBUQUERQUE (USA), SANDIA NATIONAL LABORATORY, ALBUQUERQUE (USA);JRC ISPRA ESTAB. (ITALY), POWER REACTOR AND NUCLEAR FUEL DEVELOPMENT CORP (JAPAN);KERNFORSCHUNGSZENTRUM KARLSRUHE (GERMANY);CENTRE D'ETUDES NUCLEAIR;JRC ISPRA ESTAB. (ITALY), POWER REACTOR AND NUCLEAR FUEL DEVELOPMENT CORP (JAPAN), SANDIA NATIONAL LABORATORY, ALBUQUERQUE (USA);JRC ISPRA ESTAB. (ITALY), POWER REACTOR AND NUCLEAR FUEL DEVELOPMENT CORP (JAPAN);KERNFORSCHUNGSZENTRUM KARLSRUHE (GERMANY);CENTRE D'ETUDES NUCLEAIR;KERNFORSCHUNGSZENTRUM KARLSRUHE, SANDIA NATIONAL LABORATORY, ALBUQUERQUE (USA);JRC ISPRA ESTAB. (ITALY), POWER REACTOR AND NUCLEAR FUEL DEVELOPMENT CORP (JAPAN);KERNFORSCHUNGSZENTRUM KARLSRUHE (GERMANY);CENTRE D'ETUDES NUCLEAIR
Bibliographic Reference: INTERNATIONAL TOPICAL MEETING ON FAST REACTOR SAFETY, KNOXVILLE (USA), APRIL 21-25, 1985 WRITE TO CEC LUXEMBOURG, DG XIII/A2, POB 1907 MENTIONING PAPER E 32004 ORA
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