4.5 Article

Safety verification of radiation shielding and heat transfer for a model for dry

Journal

NUCLEAR ENGINEERING AND DESIGN
Volume 291, Issue -, Pages 287-294

Publisher

ELSEVIER SCIENCE SA
DOI: 10.1016/j.nucengdes.2015.05.021

Keywords

-

Funding

  1. Specialized Research Fund for the Doctoral Program of Higher Education of China [20123218120028]
  2. Foundation of Graduate Innovation Center in NUAA [kfjj20150602]
  3. Cooperative innovation fund project of Jiangsu Province [BY2014003-04]
  4. Jiangsu Innovation Program for Graduate Education [KYLX0266]

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The goal of this research is to develop a type of dry spent fuel storage called CHN-24 container, which could contain an equivalent load of 45 GWD/MTU of spent fuel after 10 years cooling. Basically, radiation shielding performance and safe removal of decay heat, which play important roles in the safety performance, were checked and validated using the Monte Carlo method and finite element analysis to establish the radiation dose rate calculation model and three-dimensional heat transfer model for the CHN-24 container. The dose rates at the surface of the container and at a distance of 1 m from the surface were 0.42 mSv/h and 0.06 mSv/h, respectively. These conform to the International Atomic Energy Agency (IAEA) radioactive material transportation safety standards 2 mSv/h and 0.1 mSv/h. The results shows that the CHN-24 container maintains its structural and material integrity under the condition of normal thermal steady-state heat transfer as well as in case of extreme fire as evinced by transient-state analysis. The temperature inside and on the surface of the container were 150.91 degrees C and 80 degrees C under normal storage conditions, which indicated that the design also conform to IAEA heat transfer safety standards of 190 degrees C and 85 degrees C. (C) 2015 Elsevier B.V. All rights reserved.

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