60439. For information about Argonne and its pioneering science and technology programs, see www.anl.gov.
This analysis involves the examination of radionuclide release from metal fuel under conditions that would be typical of design basis and beyond design basis accidents for metal fuel, pool-type SFRs. This includes pin breach under normal operation due to defects, cladding failure at elevated temperatures due to eutectic penetration, and fuel melting conditions due to loss of heat sink/loss of flow scenarios or transient overpowers. Fuel conditions for accident scenarios that typically fall in the residual risk category or beyond for metal fuel, pool-type SFRs, such as core energetics, hypothetical core disruption accidents, or loss of sodium accidents, are not examined, as these accidents may involve very high fuel temperatures, and the possibility of fuel vaporization.Radionuclide release from metal fuel to the primary sodium is examined for fuel conditions typical of design basis and beyond design basis accidents at metal fuel, pool-type SFRs.
† The term "safety in design" is most completely described in a DOE standard for nuclear facility design, DOE-STD-1189, "Safety in Design" which describes a process for integrating safety analysis into the design process for nuclear facilities.
The following report serves as a formal introduction to the water-based Natural convection Shutdown heat removal Test Facility (NSTF) program at Argonne. Since 2005, this US Department of Energy (DOE) sponsored program has conducted large scale experimental testing to generate high-quality and traceable validation data for guiding design decisions of the Reactor Cavity Cooling System (RCCS) concept for advanced reactor designs.The most recent facility iteration, and focus of this report, is the operation of a 1 /2 scale model of a water-RCCS concept. Several features of the NSTF prototype align with the conceptual design that has been publicly released for the AREVA 625 MW t SC-HTGR. The design of the NSTF also retains all aspects common to a fundamental boiling water thermosiphon, and thus is well poised to provide necessary experimental data to advance basic understanding of natural circulation phenomena and contribute to computer code validation. Overall, the NSTF program operates to support the DOE vision of aiding US vendors in design choices of future reactor concepts, advancing the maturity of codes for licensing, and ultimately developing safe and reliable reactor technologies.In this report, the top-level program objectives, testing requirements, and unique considerations for the water cooled test assembly are discussed, and presented in sufficient depth to support defining the program's overall scope and purpose. A discussion of the proposed 6-year testing program is then introduced, which outlines the specific strategy and testing plan for facility operations. The proposed testing plan has been developed to meet the toplevel objective of conducting high-quality test operations that span across a broad range of single-and two-phase operating conditions. Details of characterization, baseline test cases, accident scenario, and parametric variations are provided, including discussions of later-stage test cases that examine the influence of geometric variations and off-normal configurations.The facility design follows, including as-built dimensions and specifications of the various mechanical and liquid systems, design choices for the test section, water storage tank, and network piping. Specifications of the instrumentation suite are then presented, along with specific information on performance windows, measurement uncertainties, and installation locations. Finally, descriptions of the control systems and heat removal networks are provided, which have been engineered to support precise quantification of energy balances and facilitate well-controlled test operations.
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