tailieunhanh - On the safety and performance demonstration tests of prototype Gen-IV sodium cooled fast reactor and validation and verification of computational codes

In this paper, the current status of test activities is described briefly and significant results are discussed. The large-scale sodium thermal-hydraulic test program, Sodium Test Loop for Safety Simulation and Assessment-1 (STELLA-1), produced satisfactory results, which were used for the computer codes V&V, and the performance test results of the model pump in sodium showed good agreement with those in water. | On the safety and performance demonstration tests of prototype Gen-IV sodium cooled fast reactor and validation and verification of computational codes

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