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Title: Post-failure phenomena in LMFBR top accidents. Final report, October 1, 1976--September 30, 1977

Abstract

Work in the area of post-failure phenomena in LMFBR TOP accidents is reported. Several different TOP-related topics are treated, including radial dependence of transient fission gas behavior in LMFBR pins; modeling of flowing-sodium pin failure tests in TREAT; gas plenum region pressurization due to sodium vaporization; and the effect of ejection rates of molten fuel from pins on the potential for extensive subassembly voiding.

Authors:
; ;
Publication Date:
Research Org.:
Virginia Univ., Charlottesville (USA). School of Engineering and Applied Science
Sponsoring Org.:
USNRC
OSTI Identifier:
5010398
Report Number(s):
NUREG/CR-0018; UVA-529058/NEEP77/103
TRN: 78-010668
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; FUEL ELEMENT FAILURE; RESEARCH PROGRAMS; FUEL-COOLANT INTERACTIONS; COMPUTER CALCULATIONS; LMFBR TYPE REACTORS; CLINCH RIVER BREEDER REACTOR; FUEL PINS; MELTING; REACTOR SAFETY; TRANSIENTS; VOIDS; ACCIDENTS; BREEDER REACTORS; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; FUEL ELEMENTS; LIQUID METAL COOLED REACTORS; PHASE TRANSFORMATIONS; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; SAFETY; SODIUM COOLED REACTORS; 220900* - Nuclear Reactor Technology- Reactor Safety; 210500 - Power Reactors, Breeding

Citation Formats

Erdman, C A, Bradley, D R, and Kelley, J L. Post-failure phenomena in LMFBR top accidents. Final report, October 1, 1976--September 30, 1977. United States: N. p., 1977. Web. doi:10.2172/5010398.
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Erdman, C A, Bradley, D R, & Kelley, J L. Post-failure phenomena in LMFBR top accidents. Final report, October 1, 1976--September 30, 1977. United States. doi:10.2172/5010398.
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Erdman, C A, Bradley, D R, and Kelley, J L. Tue . "Post-failure phenomena in LMFBR top accidents. Final report, October 1, 1976--September 30, 1977". United States. doi:10.2172/5010398. https://www.osti.gov/servlets/purl/5010398.
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@article{osti_5010398,
title = {Post-failure phenomena in LMFBR top accidents. Final report, October 1, 1976--September 30, 1977},
author = {Erdman, C A and Bradley, D R and Kelley, J L},
abstractNote = {Work in the area of post-failure phenomena in LMFBR TOP accidents is reported. Several different TOP-related topics are treated, including radial dependence of transient fission gas behavior in LMFBR pins; modeling of flowing-sodium pin failure tests in TREAT; gas plenum region pressurization due to sodium vaporization; and the effect of ejection rates of molten fuel from pins on the potential for extensive subassembly voiding.},
doi = {10.2172/5010398},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Tue Nov 01 00:00:00 EST 1977},
month = {Tue Nov 01 00:00:00 EST 1977}
}
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Technical Report:
View Technical Report (2.31 MB)
DOI:  10.2172/5010398
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  • ; ;
    The work reported was primarily aimed at establishing minimum requirements for and likelihood of large-scale voiding following fuel-pin-failure in an unprotected transient overpower (TOP) accident in a liquid-metal-cooled fast breeder reactor (LMFBR). Some attention was also given to voiding following pin failure in the low power channels of an LMFBR during the loss-of-flow-driven TOP. Initial work on early fuel motion out the pin and into sodium for both types of TOP accidents is also discussed.

  • ;
    First quarter efforts were concentrated on large-scale fission gas voiding, 2D aspects of intrasubassembly voiding, and implementation of PLUTO on the UVa. computer. (auth)

  • ; ;
    Refinements were made in the calculations of minimum molten fuel masses required for voiding. These refinements included consideration of condensation heat losses and improved modeling of flow channel geometry. The refined calculations indicate minimum molten fuel masses in excess of 3.2 gm/pin are needed for extensive voiding. Plenum gas release calculations applicable to LOF-driven-TOP and normal LOF accidents as well as to TOP accidents were formulated. Other activities included resolution of discrepancies in PLUTO calculations and attendance at several meetings at NRC's request.

  • ; ;
    Progress is summarized in studies devoted to calculating masses of molten fuel required to produce extensive subassembly voiding via a fuel-coolant-interaction (FCI). A minimum ejected mass of 1.0 to 3.0 gm/pin is estimated based on initial calculations for typical transient conditions. Work was initiated on prefailure fuel motion for very-low-burnup pins.

  • ; ; ; ...
    This Task B annual report focuses on the interaction of concrete structures and core debris which may be released in a LMFBR core disruptive accident. A heat transfer calculational technique is described and applied to the exchange of energy from hot core debris to the concrete. Predictions are compared to several test conditions for which data are available. Calculations are made of the extent to which debris can penetrate the structure prior to solidification. The Clinch River plant and the FFTF are used as two examples in the calculations. The numerical characteristics of the Sandia INTER and Westinghouse WAYER post-accidentmore » heat removal codes are scrutinized. An evaluation is made of the heat transfer characteristics exhibited in material interaction tests conducted at the Aerospace Corporation.« less