Advanced BWR core component designs and the implications for SFD analysis

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Prior to the DF-4 boiling water reactor (BWR) severe fuel damage (SFD) experiment conducted at the Sandia National Laboratories in 1986, no experimental data base existed for guidance in modeling core component behavior under postulated severe accident conditions in commercial BWRs. This paper will present the lessons learned from the DF-4 experiment (and subsequent German CORA BWR SFD tests) and the impact on core models in the current generation of SFD codes. The DF-4 and CORA BWR test assemblies were modeled on the core component designs circa 1985; that is, the 8 x 8 fuel assembly with two water rods ... continued below

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15 p.

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Ott, L.J. February 1, 1997.

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Description

Prior to the DF-4 boiling water reactor (BWR) severe fuel damage (SFD) experiment conducted at the Sandia National Laboratories in 1986, no experimental data base existed for guidance in modeling core component behavior under postulated severe accident conditions in commercial BWRs. This paper will present the lessons learned from the DF-4 experiment (and subsequent German CORA BWR SFD tests) and the impact on core models in the current generation of SFD codes. The DF-4 and CORA BWR test assemblies were modeled on the core component designs circa 1985; that is, the 8 x 8 fuel assembly with two water rods and a cruciform control blade constructed of B{sub 4}C-filled tubelets. Within the past ten years, the state-of-the-art with respect to BWR core component development has out-distanced the current SFD experimental data base and SFD code capabilities. For example, modern BWR control blade design includes hafnium at the tips and top of each control blade wing for longer blade operating lifetimes; also water rods have been replaced by larger water channels for better neutronics economy; and fuel assemblies now contain partial-length fuel rods, again for better neutronics economy. This paper will also discuss the implications of these advanced fuel assembly and core component designs on severe accident progression and on the current SFD code capabilities.

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15 p.

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INIS; OSTI as DE97002970

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  • AICHE/ASME national heat transfer conference: current developments in numerical simulation of heat and mass transfer, Baltimore, MD (United States), 10-12 Aug 1997

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  • Other: DE97002970
  • Report No.: CONF-970824--2
  • Grant Number: AC05-96OR22464
  • Office of Scientific & Technical Information Report Number: 510431
  • Archival Resource Key: ark:/67531/metadc696072

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Office of Scientific & Technical Information Technical Reports

Reports, articles and other documents harvested from the Office of Scientific and Technical Information.

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  • February 1, 1997

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  • Aug. 14, 2015, 8:43 a.m.

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  • April 7, 2016, 7:31 p.m.

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Ott, L.J. Advanced BWR core component designs and the implications for SFD analysis, article, February 1, 1997; Tennessee. (digital.library.unt.edu/ark:/67531/metadc696072/: accessed October 18, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.