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in creator/contributor: "Seiffert, S.L."  
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Light water reactor fuel response during reactivity initiated accident experiments

Description: Experimental results from six recent Power Burst Facility (PBF) reactivity initiated accident (RIA) tests are compared with data from previous Special Power Excursion Reactor Test (SPERT), and Japanese Nuclear Safety Research Reactor (NSRR) tests. The RIA fuel behavior experimental program recently started in the PBF is being conducted with coolant conditions typical of hot-startup conditions in a commercial boiling water reactor. The SPERT and NSRR test programs investigated the behavior of si… more
Date: January 1, 1979
Creator: MacDonald, P. E.; McCardell, R. K.; Martinson, Z. R. & Seiffert, S. L.
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Partner: UNT Libraries Government Documents Department
open access

Assessment of light water reactor fuel damage during a reactivity initiated accident

Description: This paper presents an assessment of LWR fuel damage during a reactivity initiated accident and comments on the adequacy of the present USNRC design requirements. Results from early SPERT tests are reviewed and compared with results from recent computer simulations and PBF tests. A progression of fuel rod and cladding damage events is presented. High strain rate deformation of relatively cool irradiated cladding early in the transient may result in fracture at a radial average peak fuel enthalp… more
Date: January 1, 1980
Creator: MacDonald, P. E.; Seiffert, S. L.; Martinson, Z. R.; McCardell, R. K.; Owen, D. E. & Fukuda, S. K.
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Partner: UNT Libraries Government Documents Department
open access

Light water reactor fuel response during reactivity initiated accident experiments

Description: Experimental results from six recent Power Burst Facility (PBF) reactivity initiated accident (RIA) tests are compared with data from previous SPERT, TREAT and NSRR programs. The RIA fuel behavior experimental program recently started in the PBF is being conducted with coolant conditions typical of hot-startup conditions in a commercial boiling water reactor. The SPERT, TREAT and NSRR test programs investigated the behavior of single or small clusters of light water reactor (LWR) type fuel rods… more
Date: January 1, 1979
Creator: MacDonald, P. E.; McCardell, R. K.; Martinson, Z. R.; Hobbins, R. R.; Seiffert, S. L. & Cook, B. A.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Behavior of defective LWR-type fuel rods irradiated under postulated accident conditions

Description: The irradiation experiments reported here have been conducted by the Thermal Fuels Behavior Program of EG and G Idaho, Inc., for the United States Nuclear Regulatory Commission in the Power Burst Facility (PBF) at the Idaho National Engineering Laboratory. Five of the rods were irradiated in PCM tests and one in a LOC test. During these tests, the six rods lost cladding integrity prior to or during the transient phase of the test due to either manufacturing defects or intentional rod design and… more
Date: May 1, 1979
Creator: Hobbins, R. R.; Croucher, D. W.; Seiffert, S. L.; Cook, B. A.; Kerwin, D. K.; Mehner, A. S. et al.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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