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[ASME 18th International Conference on Nuclear Engineering - Xi’an, China (May 17–21, 2010)] 18th International Conference on Nuclear Engineering: Volume 3 - Thermal Hydraulic Analysis Towards a Robust Design of Leak Collection Tray for Pool Type Sodium Cooled Fast Reactors

[ASME 18th International Conference on Nuclear Engineering - Xi’an, China (May 17–21, 2010)] 18th International Conference on Nuclear Engineering: Volume 3 - Thermal Hydraulic Analysis Towards a Robust Design of Leak Collection Tray for Pool Type Sodium Cooled Fast Reactors

Sharma, Anil Kumar; Velusamy, K.; Kasinathan, N.; Chellapandi, P.; Chetal, S. C.; Raj, Baldev
  • 作者Sharma, Anil Kumar; Velusamy, K.; Kasinathan, N.; Chellapandi, P.; Chetal, S. C.; Raj, Baldev
  • 文件大小958.07KB
  • 发表时间2010
  • DOI10.1115/icone18-29294
  • 页码421-428
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