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Proceedings Papers
ASME 2017 Nuclear Forum collocated with the ASME 2017 Power Conference Joint With ICOPE-17, the ASME 2017 11th International Conference on Energy Sustainability, and the ASME 2017 15th International Conference on Fuel Cell Science, Engineering and Technology
June 26–30, 2017
Charlotte, North Carolina, USA
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-4059-7
ASME 2017 Nuclear Forum
Codes, Standards, Licensing and Regulatory Compliance
ASME PTC 46 Performance Tests in Digital Plant Context
ICONE 2017; V009T01A001https://doi.org/10.1115/NUCLRF2017-3245
Topics:
Testing performance
,
Doors
,
Performance test codes
,
Power stations
,
Transparency
Structures, Components and Materials
Investigation on Creep Mechanisms of Alloy 709
ICONE 2017; V009T02A003https://doi.org/10.1115/NUCLRF2017-3649
Topics:
Alloys
,
Creep
,
Stress
,
Temperature
,
Grain boundary diffusion
,
Dislocations
,
Generation IV reactors
,
Iron
,
Mechanical properties
,
Nuclear reactors
Thermal Hydraulics and Computational Fluid Dynamics
A Statistical Method for Benchmarking Nuclear Plant Models, Using ACAP
ICONE 2017; V009T03A001https://doi.org/10.1115/NUCLRF2017-3266
Topics:
Computers
,
Coolants
,
Design
,
Errors
,
Fluids
,
Nuclear power stations
,
Nuclear reactors
,
Steady state
,
Transients (Dynamics)
,
Uncertainty
Improvement of the RELAP5-3D Model of Condensation in the Presence of Noncondensables
ICONE 2017; V009T03A002https://doi.org/10.1115/NUCLRF2017-3401
Topics:
Condensation
,
Vapors
,
Accidents
,
Density
,
Nuclear power stations
,
Pressure
,
Pressurized water reactors
,
Steam
,
Boilers
,
Coolants
Solution of Governing Equations for Six-Field System Code
ICONE 2017; V009T03A004https://doi.org/10.1115/NUCLRF2017-3515
Topics:
Accidents
,
Algebra
,
Boiling
,
Bubbles
,
Computer software
,
Computers
,
Condensation
,
Coolants
,
Cooling
,
Design
Flow Testing and Analysis of the FSP-1 Experiment
ICONE 2017; V009T03A005https://doi.org/10.1115/NUCLRF2017-3639
Topics:
Flow (Dynamics)
,
Testing
,
Fuels
,
Plates (structures)
,
Uranium
,
Alloys
,
Aluminum
,
Molybdenum
,
Orifices
,
Pressure
Experimental Study on Heat Transfer to Supercritical CO2 Flowing in Vertical Upward Tube at Medium Mass Flux
ICONE 2017; V009T03A006https://doi.org/10.1115/NUCLRF2017-3664
Topics:
Heat transfer
,
Supercritical carbon dioxide
,
Heat flux
,
Pressure
,
Buoyancy
,
Carbon dioxide
,
Wall temperature
,
Heat transfer coefficients
,
Density
,
Fluids