Thermal-Hydraulic Experiments Using A Dry Cask Simulator (NUREG/CR-7250)

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Publication Information

Manuscript Completed: October 2018
Date Published: October 2018

Prepared by:
S. G. Durbin
E. R. Lindgren

Sandia National Laboratories
Albuquerque, NM 87185

Shawn Marshall, NRC Project Manager

Office of Nuclear Regulatory Research
U.S. Nuclear Regulatory Commission
Washington DC 20555-0001

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A series of well-controlled tests were conducted using a single, prototypic-geometry boiling water reactor (BWR) fuel assembly inside of a pressure vessel and enclosure to mimic the thermal-hydraulic responses of both aboveground and belowground dry storage casks. This is simplified test assembly was shown to have simlarity with prototypic systems through dimensional analysis. The data were collected over a broad parameter set including simulated decay power and internal helium pressure. These data were collected and documented with the intent to be used for validation exercise with thermal-hydraulic codes and computational fluid dynamics simluations. The primary values of interest, air mass flow rate and peak cladding temperature, and their uncertainties are highlighed in this report.

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