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OSTI.GOV Journal Article: Thermohydraulic characteristics of the BN-600 reactor at the Beloyarsk nuclear power station Thermohydraulic characteristics of the
Thermo-Hydraulic Optimisation of the EURISOL-DS MMW Hg targetThe present document describes the thermal and the stress analysis of the final design of the
OSTI.GOV Conference: Proceedings of the 7th International Meeting on Nuclear Reactor Thermal-Hydraulics NURETH-7. Volume 3, Sessions 12-16
OSTI.GOV Technical Report: Thermohydraulic LMFBR safety experiments. Quarterly report, July-- September 1975 Thermohydraulic LMFBR safety experiments. Quarter
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E.Uspuras,,A.Kaliatka,,G.Du-( )ndulis.Analysis of potential water hammer at the Ignalina NPP using thermal -hydraulic and structural analysis codes
OSTI.GOV Conference: Loss-of-fluid test findings in pressurized water reactor cores thermal-hydraulic behavior Loss-of-fluid test findings in pressurized
thermohydraulic phenomena often are mischaracterized as water hammer.The observed damage includes mechanical damage,thermal shock,and high cycle fatigue.Water
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OSTI.GOV Technical Report: SSC: an advanced thermohydraulic transient code for LMFBRs. Quarterly progress report, April 1--June 30, 1976
OSTI.GOV Technical Report: SSC: an advanced thermohydraulic transient code for LMFBRs. Quarterly progress report, January 1--March 31, 1976
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Numerical Investigation for Net Enhancement in Thermal-Hydraulic Performance of Compact Fin-Tube Heat Exchangers with Vortex Generators
thermal-hydraulics/neutron-kinetics of boiling water(NK) core models with system transient thermal- Validation of Coupled Thermal-Hydraulic and
Request PDF on ResearchGate | A particle-image velocimetry system for measurement of velocity flow fields for investigations of thermohydraulic processes on
Atomic energy, thermal-hydraulic transients program and emergency core cooling systems-reflood program : agreement between the United States of America and
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B131 Thermal-hydraulic analysis on reactor upper plenum of MONJUKei HONDA, Takero MORI, Masutake SOTSU, Hiroaki OHIRA Author information
OSTI.GOV Technical Report: SSC. Advanced thermohydraulic transient code for LMFBRs. Quarterly progress report, July 1--September 30, 1975
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Neutronics and sub-channel thermal-hydraulics analysis of the Iranian VVER-1000 fuel bundleNeutronics and sub-channel thermal-hydraulics analysis of the
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