Ivor D. Clifford, Ph.D.
Affiliations: | 2013 | Mechanical and Nuclear Engineering | Pennsylvania State University, State College, PA, United States |
Area:
Nuclear Engineering, Mechanical EngineeringGoogle:
"Ivor Clifford"Parents
Sign in to add mentor| Kostadin Ivanov | grad student | 2013 | Penn State | |
| (A hybrid coarse and fine mesh solution method for prismatic high temperature gas-cooled reactor thermal-fluid analysis.) | ||||
BETA: Related publications
See more...
Publications
|
You can help our author matching system! If you notice any publications incorrectly attributed to this author, please sign in and mark matches as correct or incorrect. |
| Scolaro A, Clifford I, Fiorina C, et al. (2020) The OFFBEAT multi-dimensional fuel behavior solver Nuclear Engineering and Design. 358: 110416 |
| Perret G, Wicaksono D, Clifford ID, et al. (2019) Global Sensitivity and Registration Strategy for Temperature Profile of Reflood Experiment Simulations Nuclear Technology. 205: 1638-1651 |
| Clifford I, Pecchia M, Mukin R, et al. (2019) Studies on the effects of local power peaking on heat transfer under dryout conditions in BWRs Annals of Nuclear Energy. 130: 440-451 |
| Shama A, Pouchon MA, Clifford I. (2019) Simulation of the microfluidic mixing and the droplet generation for 3D printing of nuclear fuels Additive Manufacturing. 26: 1-14 |
| Clifford I, Pecchia M, Puragliesi R, et al. (2018) On the characteristics of the flow and heat transfer in the core bypass region of a PWR Nuclear Engineering and Design. 330: 117-128 |
| Mukin R, Clifford I, Zerkak O, et al. (2018) Modeling and analysis of selected organization for economic cooperation and development PKL-3 station blackout experiments using TRACE Nuclear Engineering and Technology. 50: 356-367 |
| Fiorina C, Clifford I, Aufiero M, et al. (2015) GeN-Foam: a novel OpenFOAM® based multi-physics solver for 2D/3D transient analysis of nuclear reactors Nuclear Engineering and Design. 294: 24-37 |
| Geuss M, Panzer HKF, Clifford ID, et al. (2014) Parametric model order reduction using pseudoinverses for the matrix interpolation of differently sized reduced models Ifac Proceedings Volumes (Ifac-Papersonline). 19: 9468-9473 |
| Aufiero M, Brovchenko M, Cammi A, et al. (2014) Calculating the effective delayed neutron fraction in the Molten Salt Fast Reactor: Analytical, deterministic and Monte Carlo approaches Annals of Nuclear Energy. 65: 78-90 |
| Clifford I, Ivanov KN, Avramova MN. (2013) A multi-scale homogenization and reconstruction approach for solid material temperature calculations in prismatic high temperature reactor cores Nuclear Engineering and Design. 256: 1-13 |