MODELING A SPENT NUCLEAR FUEL CASK SEISMIC TEST

被引:0
作者
Klymyshyn, Nicholas [1 ]
Kadooka, Kevin [1 ]
Fitzpatrick, James [1 ]
Spitz, Casey [1 ]
机构
[1] Pacific Northwest Natl Lab, Richland, WA 99354 USA
来源
PROCEEDINGS OF ASME 2023 PRESSURE VESSELS & PIPING CONFERENCE, PVP2023, VOL 6 | 2023年
关键词
Spent nuclear fuel; seismic analysis; finite element analysis;
D O I
暂无
中图分类号
TH [机械、仪表工业];
学科分类号
0802 ;
摘要
The US Department of Energy Spent Fuel and Waste Science and Technology (SFWST) program is planning to conduct a series of full-scale shake table tests to simulate hypothetical earthquake conditions and record the response of surrogate spent nuclear fuel (SNF) assemblies in a canister dry storage system mockup. The shake table motions will represent a range of hypothetical earthquake conditions at hypothetical locations in the continental US to generally define the range of mechanical loads that SNF can be expected to experience during extended dry storage periods. The earthquake conditions will represent seismic hazards in the 2,000-to-20,000-year return period range. The test will use instrumented pressurized water reactor (PWR) fuel assemblies with surrogate mass inside the fuel rods instead of radioactive fuel pellets. Dummy assemblies with similar mass and dimensions to actual fuel assemblies will occupy the rest of the fuel assembly locations in a SNF canister that holds 32 fuel assemblies. The canister will be located inside a mockup vertical concrete cask (VCC). Instrumentation will record the motion of the major components of the complex dynamic system, and strain gauges will be used to record the cladding strain at selected locations. Preparations for the test require modeling predictions to identify the range of response of the system and to help select specific earthquake ground motion cases to be simulated on the shake table from a larger set of potential cases. This paper describes the pretest nonlinear finite element modeling efforts that have been completed to date, including cask system level modeling and fuel assembly modeling in LS-DYNA. The cask system level models are critical for anticipating sliding or tipping of an unanchored cask during the test. The fuel assembly model is needed to estimate the range of cladding strain response and fuel assembly structural response to be expected during the test and cladding strain measurements will be key metrics for model validation and the development of modeling best practices after the test is concluded.
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页数:6
相关论文
共 6 条
  • [1] Kadooka K., 2022, PNNL-32986
  • [2] Kalinina E., 2020, Surrogate Assembly 30 cm Drop Test
  • [3] Kalinina E.A., 2018, SFWD-SFWST-2018-000494
  • [4] Klymyshyn N.A., 2018, PNNL-28088
  • [5] Klymyshyn N.A., 2021, PNNL-32087
  • [6] Klymyshyn N.A., 2022, PNNL-33220