Implementation of Hydrogen Solid Solubility Data and Precipitation Threshold Stresses in the Fuel Rod Code TESPA-ROD
ASME J of Nuclear Rad Sci.
2019
5(2)
Investigations of neutron noise induced by transient cross flow in a PWR reactor core
18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics
2019
A correlation of the water film thickness and friction factor for supercritical /subcritical transition in a hot-leg pipe geomtery
18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics
NURETH 2019
2019
Neutron physical feasibility of small modular design of dual fluid reactor
International Conference on Nuclear Engineering,
ICONE, 2019-May
2019
Implementation of piN power factors in the ANSYS CFX/PARCS coulpling system for local analysis of neutron oscillation
International Conference on Nuclear Engineering,
ICONE, 2019-May
2019
Integration of the subchannel thermal-hydraulic code SubChanFlow into the reactor dynamics code PARCS: Development and testing based on a computational benchmark
Progress in Nuclear Energy
2019
Preliminary hydraulic analysis of the distribution zone in the Dual Fluid Reactor concept
Progress in Nuclear Energy
2019
110
Feasibility Study on Conceptual Design of Dual Fluid Fast Reactor
Hedongli Gongcheng/Nuclear Power Engineering
2019
40 (1)
On CCFL at a PWR Hot-Leg Pipe Geometry and Comparison Between Results in COLLIDER 1/4th- and Kobe 1/15th-Scaled Facilities
Nuclear Science and Engineering
2019
193 (1-2)
Neutron physics of the liquid-fuel heat-pipe reactor concept with molten salt fuel—Static calculations
International Journal of Energy Research
2019
43 (14)