Experiments to investigate direct containment heating phenomena with scaled models of the Zion Nuclear Power Plant in the Surtsey Test Facility

• Main Authors: Allen, M. D., Pilch, M. M., Blanchat, T. K., Griffith, R. O., Nichols, R. T.
• Other Authors: U.S. Nuclear Regulatory Commission
• Format: Report
• Language: English
• Published: U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Systems Research. 1994
• Subjects: Corium; 210200; Experimental Data 220900; Mathematical Models; Reactor Safety; Pressure Measurement; 21 Specific Nuclear Reactors And Associated Plants; Scale Models; Simulation; Zion-1 Reactor; Measuring Instruments; Containment Systems; 22 General Studies Of Nuclear Reactors; Design; Power Reactors; Nonbreeding; Light-Water Moderated; Nonboiling Water Cooled; Thermal Analysis; Meltdown; Zion-2 Reactor; Temperature Measurement; Surtsey
• Online Access: https://doi.org/10.2172/10158784; https://digital.library.unt.edu/ark:/67531/metadc1388166/

The Surtsey Facility at Sandia National Laboratories (SNL) is used to perform scaled experiments that simulate hypothetical high-pressure melt ejection (HPME) accidents in a nuclear power plant (NPP). These experiments are designed to investigate the effect of specific phenomena associated with direct containment heating (DCH) on the containment load, such as the effect of physical scale, prototypic subcompartment structures, water in the cavity, and hydrogen generation and combustion. In the Integral Effects Test (IET) series, 1:10 linear scale models of the Zion NPP structures were constructed in the Surtsey vessel. The RPV was modeled with a steel pressure vessel that had a hemispherical bottom head, which had a 4-cm hole in the bottom head that simulated the final ablated hole that would be formed by ejection of an instrument guide tube in a severe NPP accident. Iron/alumina/chromium thermite was used to simulate molten corium that would accumulate on the bottom head of an actual RPV. The chemically reactive melt simulant was ejected by high-pressure steam from the RPV model into the scaled reactor cavity. Debris was then entrained through the instrument tunnel into the subcompartment structures and the upper dome of the simulated reactor containment building. The results of the IET experiments are given in this report.