Release of fission products during controlled loss-of-coolant accidents and hypothetical core meltdown accidents. [PWR; BWR]
Conference
·
OSTI ID:6515498
A few years ago the Projekt Nukleare Sicherheit joined the United States Nuclear Regulatory Commission in the development of a research program which was designed to investigate fission product release from light water reactor fuel under conditions ranging from spent fuel shipping cask accidents to core meltdown accidents. Three laboratories have been involved in this cooperative effort. At Argonne National Laboratory (ANL), the research effort has focused on noble gas fission product release, whereas at Oak Ridge National Laboratory (ORNL) and at Kernforschungszentrum Karlsruhe (KfK), the studies have emphasized the release of species other than the noble gases. In addition, the ORNL program has been directed toward the development of fission product source terms applicable to analyses of spent fuel shipping cask accidents and controlled loss-of-coolant accidents, and the KfK program has been aimed at providing similar source terms which are characteristic of core meltdown accidents. The ORNL results are presented for fission product release from defected fuel rods into a steam atmosphere over the temperature range 500 to 1200/sup 0/C, and the KfK results for release during core meltdown sequences.
- Research Organization:
- Kernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.); Oak Ridge National Lab., TN (USA)
- DOE Contract Number:
- W-7405-ENG-26
- OSTI ID:
- 6515498
- Report Number(s):
- CONF-781147-1
- Country of Publication:
- United States
- Language:
- English
Similar Records
(Boiling water reactor (BWR) CORA experiments)
(Installation of a boiling water reactor core melt progression phenomena program)
Evaluation of containment failure modes and fission product releases during core meltdown accidents in a BWR with a Mark III containment
Technical Report
·
Tue Oct 16 00:00:00 EDT 1990
·
OSTI ID:6434331
(Installation of a boiling water reactor core melt progression phenomena program)
Technical Report
·
Thu Jun 07 00:00:00 EDT 1990
·
OSTI ID:6954867
Evaluation of containment failure modes and fission product releases during core meltdown accidents in a BWR with a Mark III containment
Conference
·
Mon Dec 31 23:00:00 EST 1984
·
OSTI ID:6188199
Related Subjects
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