Power excursion analysis for high burnup cores

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A study was undertaken of power excursions in high burnup cores. There were three objectives in this study. One was to identify boiling water reactor (BWR) and pressurized water reactor (PWR) transients in which there is significant energy deposition in the fuel. Another was to analyze the response of BWRs to the rod drop accident (RDA) and other transients in which there is a power excursion. The last objective was to investigate the sources of uncertainty in the RDA analysis. In a boiling water reactor, the events identified as having significant energy deposition in the fuel were a rod drop ... continued below

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76 p.

Creation Information

Diamond, D. J.; Neymotin, L. & Kohut, P. February 1996.

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This report is part of the collection entitled: Office of Scientific & Technical Information Technical Reports and was provided by UNT Libraries Government Documents Department to Digital Library, a digital repository hosted by the UNT Libraries. It has been viewed 12 times . More information about this report can be viewed below.

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  • U.S. Nuclear Regulatory Commission
    Publisher Info: Nuclear Regulatory Commission, Washington, DC (United States). Div. of Engineering and Systems Technology
    Place of Publication: Washington D.C.
  • Brookhaven National Laboratory
    Publisher Info: Brookhaven National Lab., Upton, NY (United States)
    Place of Publication: Upton, New York

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Description

A study was undertaken of power excursions in high burnup cores. There were three objectives in this study. One was to identify boiling water reactor (BWR) and pressurized water reactor (PWR) transients in which there is significant energy deposition in the fuel. Another was to analyze the response of BWRs to the rod drop accident (RDA) and other transients in which there is a power excursion. The last objective was to investigate the sources of uncertainty in the RDA analysis. In a boiling water reactor, the events identified as having significant energy deposition in the fuel were a rod drop accident, a recirculation flow control failure, and the overpressure events; in a pressurized water reactor, they were a rod ejection accident and boron dilution events. The RDA analysis was done with RAMONA-4B, a computer code that models the space- dependent neutron kinetics throughout the core along with the thermal hydraulics in the core, vessel, and steamline. The results showed that the calculated maximum fuel enthalpy in high burnup fuel will be affected by core design, initial conditions, and modeling assumptions. The important uncertainties in each of these categories are discussed in the report.

Physical Description

76 p.

Notes

INIS; OSTI as TI96007749

Source

  • Other Information: PBD: Feb 1996

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  • Other: TI96007749
  • Report No.: NUREG/CR--6422
  • Report No.: BNL-NUREG--52491
  • Grant Number: AC02-76CH00016
  • DOI: 10.2172/207613 | External Link
  • Office of Scientific & Technical Information Report Number: 207613
  • Archival Resource Key: ark:/67531/metadc672417

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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.

Office of Scientific and Technical Information (OSTI) is the Department of Energy (DOE) office that collects, preserves, and disseminates DOE-sponsored research and development (R&D) results that are the outcomes of R&D projects or other funded activities at DOE labs and facilities nationwide and grantees at universities and other institutions.

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Creation Date

  • February 1996

Added to The UNT Digital Library

  • June 29, 2015, 9:42 p.m.

Description Last Updated

  • April 8, 2016, 1:02 p.m.

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Diamond, D. J.; Neymotin, L. & Kohut, P. Power excursion analysis for high burnup cores, report, February 1996; Washington D.C.. (digital.library.unt.edu/ark:/67531/metadc672417/: accessed October 23, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.