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Keyword [CANDU]
Result: 21 - 38 | Page: 2 of 2
21.
A study of intermittent buoyancy induced flow phenomena in CANDU fuel channels
22.
Analysis of power variation in a CANDU-6 with a loss of moderator
23.
A thermomechanical model of CANDU fuel
24.
Modelling of corrosion and iron transport in the primary heat transport system of CANDU reactors
25.
Experimental and numerical study of hydrodynamics of flow-accelerated corrosion in CANDU primary coolant
26.
FAST: A Fuel And Sheath Modeling Tool for CANDU Reactor Fuel
27.
Investigations on flow and flow-induced vibration of CANDU fuel bundles
28.
Modelisation thermohydraulique et simulation numerique d'un canal de combustible des reacteurs nucleaires CANDU
29.
Analysis of a CANDU nuclear steam system at low power for assessment of heat transport header temperature measurements
30.
Development of an on-line fuel failure monitoring system for CANDU reactors
31.
Neutronics-thermalhydraulics coupling in a CANDU SCWR
32.
Assessing the impact of transport time between failed fuel and delayed neutron detectors in CANDU reactors
33.
Quench of cylindrical tubes during transition from film to nucleate boiling heat transfer in CANDU reactor core
34.
Numerical and experimental investigations on vibration of simulated CANDU fuel bundles subjected to turbulent fluid flow
35.
Etude de surete du SCWR par prise en compte du couplage neutronique-thermohydraulique
36.
Modeling and simulation of CANDU reactor and its regulating system
37.
Optimal fuel management of CANDU reactors at approach to refuelling equilibrium: An investigation into the optimal use of advanced fuels in the CANDU-6 reactor
38.
OPTIMAL THORIUM-FUELED CANDU NUCLEAR REACTOR FUEL MANAGEMENT
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