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Approaches, Relevant Topics, and Internal Method for Uncertainty Evaluation in Predictions of Thermal-Hydraulic System Codes
Uncertainty Evaluation Thermal-Hydraulic System Codes
2009/9/3
The evaluation of uncertainty constitutes the necessary supplement of best-estimate calculations performed to understand accident scenarios in water-cooled nuclear reactors. The needs come from the im...
Evaluation of Heat Removal from RBMK-1500 Core Using Control Rods Cooling Circuit
Heat Removal RBMK-1500 Core
2009/9/3
The Ignalina nuclear power plant is a twin unit with two RBMK-1500, graphite moderated, boiling water, multichannel reactors. After the decision was made to decommission the Ignalina NPP, Unit 1 was s...