Preliminary data analysis of surrogate fuel-loaded road transportation tests under normal conditions of transport
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In this study, road transportation tests were conducted with surrogate fuel assemblies under normal conditions of transport to evaluate the vibration and shock load characteristics of spent nuclear fuel (SNF). The overall test data analysis was conducted based on the measured acceleration and strain data obtained from the speed bump, lane-change, deceleration, obstacle avoidance, and circular tests. Furthermore, representative shock response spectrums and power spectral densities of each test mode were acquired. Amplification or attenuation characteristics were investigated according to the load transfer path. The load attenuated significantly as it transferred from the trailer to the cask. By contrast, the load amplified as it transferred from the cask to the surrogate SNF assembly. The fuel loading location on the cask disk assembly did not exhibit a significant influence on the strain measured from the fuel rods. The principal strain was in the vertical direction, and relatively large strain values were obtained in spans with large spacing between spacer grids. The influence of the lateral location of fuel rods was also investigated. The fuel rods located at the side exhibited relatively large strain values than those located at the center. Based on the strain data obtained from the test results, a hypothetical road transportation scenario was established. A fatigue evaluation of the SNF rod was performed based on this scenario. The evaluation results indicate that no fatigue damage occurred on the fuel rods.
Abstract
In this study, road transportation tests were conducted with surrogate fuel assemblies under normal conditions of transport to evaluate the vibration and shock load characteristics of spent nuclear fuel (SNF). The overall test data analysis was conducted based on the measured acceleration and strain data obtained from the speed bump, lane-change, deceleration, obstacle avoidance, and circular tests. Furthermore, representative shock response spectrums and power spectral densities of each test mode were acquired. Amplification or attenuation characteristics were investigated according to the load transfer path. The load attenuated significantly as it transferred from the trailer to the cask. By contrast, the load amplified as it transferred from the cask to the surrogate SNF assembly. The fuel loading location on the cask disk assembly did not exhibit a significant influence on the strain measured from the fuel rods. The principal strain was in the vertical direction, and relatively large strain values were obtained in spans with large spacing between spacer grids. The influence of the lateral location of fuel rods was also investigated. The fuel rods located at the side exhibited relatively large strain values than those located at the center. Based on the strain data obtained from the test results, a hypothetical road transportation scenario was established. A fatigue evaluation of the SNF rod was performed based on this scenario. The evaluation results indicate that no fatigue damage occurred on the fuel rods.
참고문헌 (17)
- Nuclear Safety and Security Commission, "Regulation on the Delivery of Spent Nuclear Fuel", NSSC Notice No. 2017-64, ~ (2017)
- U.S. Nuclear Regulatory Commission, "Packaging and Transportation of Radioactive Material, Title 10, Code of Federal Regulation, Part 71", ~ (1999)
- Shock and Vibration Environments for a Large Shipping Container during Truck Transport (Part II), "C.E. Magnuson", Sandia National Laboratories, ~, pp.NUREG (1978), CR-0128, SAND78-0337
- A Method for Determining the Spent-Fuel Contribution to Transport Cask Containment Requirements, "T. L. Sanders", Sandia National Labs, ~, pp.SAND90-2406 (1992)
- 임재훈, "정상운반조건의 진동 및 충격하중을 고려한 사용후핵연료의 구조적 건전성 시험평가 해외연구현황", Journal of Nuclear Fuel Cycle and Waste Technology, 17(2), pp.167~181 (2019), 한국방사성폐기물학회[DOI]
- Fuel-Assembly Shaker Test Plan-Tests for Determining Loads on Used Nuclear Fuel under Normal Conditions of Transport, "P. McConnell", ~, pp.FCRD-UFD-2012-000341 (2012)
- Fuel Assembly Shaker Test for Determining Loads on a PWR Assembly under Surrogate Normal Conditions of Truck Transport, "P. McConnell", 2013~, pp.SAND2013-5210P (2013)
- Normal Conditions of Transport Truck Test of a Surrogate Fuel Assembly, "P. McConnell", Sandia National Laboratories (SNL-NM), ~, pp.FCRD-UFD-2014-000066 (2014)
- Surrogate Fuel Assembly Multi-Axis Shaker Tests to Simulate Normal Conditions of Rail and Truck Transport, "P. McConnell", Sandia National Lab (SNL-NM), ~, pp.FCRD-UFRD-2015-00128 (2016)
- Used Nuclear Fuel Loading and Structural Performance under Normal Conditions of Transport-Demonstration of Approach and Results on Used Fuel Performance, "H. Adkins", USDOE Office of Nuclear Energy (NE), ~, pp.FCRD-UFD-2013-000325 (2013)
- N. Klymyshyn, "Normal transport loads on casks and fuel assemblies", EPRI ESCP Meeting (2014)
- Used Fuel Rail Shock and Vibration Testing Options Analysis, "S.B. Ross", Pacific Northwest National Lab (PNNL), ~, pp.FCRD-UFD-2014-000327 (2014)
- P. McConnell, "ENSA ENUN 32P rail-cask transport tests start June 2017", Spent Fuel and Waste Science and Technology, ~ (2017)
- Data Analysis of ENSA, "DOE Rail Cask Tests", E.A. Kalinina, 2018, SFWD-SFWST-2018-000494
- Modeling and Analysis of the ENSA, "DOE Multimodal Transportation Campaign", N.A. Klymyshyn, 2018, PNNL-28088
- "ISO 14791, Road Vehicles Heavy Commercial Vehicle Combinations and Articulated BuseseLateral Stability Test Method", ~ (2000)
- "Code GlyphWorks Reference Guide", ~ (2021)
