Query

Active Filters

  • (-) PSI Laboratories = Thermal Hydraulics LTH
  • (-) PSI Laboratories ≠ Spallation Neutron Source ASQ
Search Results 1 - 20 of 312

Pages

  • RSS Feed
Select Page
Synthesis of a CFD benchmark exercise based on a test in the PANDA facility addressing the stratification erosion by a vertical jet in presence of a flow obstruction
Andreani, M., Gaikwad, A. J., Ganju, S., Gera, B., Grigoryev, S., Herranz, L. E., … Zhang, R. (2019). Synthesis of a CFD benchmark exercise based on a test in the PANDA facility addressing the stratification erosion by a vertical jet in presence of a flow obstruction. Nuclear Engineering and Design, 354, 110177 (31 pp.). https://doi.org/10.1016/j.nucengdes.2019.110177
Pool CFD modelling: lessons from the SESAME project
Moreau, V., Profir, M., Alemberti, A., Frignani, M., Merli, F., Belka, M., … Martelli, D. (2019). Pool CFD modelling: lessons from the SESAME project. Nuclear Engineering and Design, 355, 110343 (12 pp.). https://doi.org/10.1016/j.nucengdes.2019.110343
Uncertainties in pressurized thermal shock analyses
Niffenegger, M., Garrido, O. C., Mora, D. F., Qian, G., Mukin, R., Sharabi, M., … Niceno, B. (2019). Uncertainties in pressurized thermal shock analyses. In PVP - American Society of Mechanical Engineers. Pressure vessels and piping division: Vol. 3. Design and analysis: 4th international symposium on coke drum life cycle management (pp. PVP2019-94076 (10 pp.). https://doi.org/10.1115/PVP2019-94076
Evaluation of the PAR mitigation system in Swiss PWR containment using the GOTHIC code
Papini, D., Andreani, M., Steiner, P., Ničeno, B., Klügel, J. U., & Prasser, H. M. (2019). Evaluation of the PAR mitigation system in Swiss PWR containment using the GOTHIC code. Nuclear Technology, 205(1-2), 153-173. https://doi.org/10.1080/00295450.2018.1505356
Multi-step planning calculations with the GOTHIC code used for the design of complex experiments in the PANDA facility
Andreani, M., Paladino, D., & Papini, D. (2018). Multi-step planning calculations with the GOTHIC code used for the design of complex experiments in the PANDA facility. Nuclear Engineering and Design, 339, 116-125. https://doi.org/10.1016/j.nucengdes.2018.09.005
Corrective interface tracking approach to simulate finite-size bubbly flows
Badreddine, H., Lafferty, N., Ničeno, B., & Prasser, H. M. (2018). Corrective interface tracking approach to simulate finite-size bubbly flows. Chemical Engineering Science, 178, 61-69. https://doi.org/10.1016/j.ces.2017.12.028
Simulations of droplet merging with free surface and bubble column reactor with finite-size Lagrangian particle tracking
Badreddine, H., & Ničeno, B. (2018). Simulations of droplet merging with free surface and bubble column reactor with finite-size Lagrangian particle tracking. Chemical Engineering Science, 176, 609-621. https://doi.org/10.1016/j.ces.2017.10.037
Large scale experiments representing a containment natural circulation loop during an accident scenario
Kapulla, R., Mignot, G., Paranjape, S., Andreani, M., & Paladino, D. (2018). Large scale experiments representing a containment natural circulation loop during an accident scenario. Science and Technology of Nuclear Installations, 2018, 8989070 (12 pp.). https://doi.org/10.1155/2018/8989070
PIV measurements in the vicinity of a steam sparger in the PANDA facility
Kapulla, R., Uong, D., Zimmer, C., & Paladino, D. (2018). PIV measurements in the vicinity of a steam sparger in the PANDA facility. Nuclear Engineering and Design, 336, 112-121. https://doi.org/10.1016/j.nucengdes.2017.07.003
Monte Carlo simulation of a scintillation detector for spent fuel characterization in a hot cell
Papadionysiou, M., Perret, G., Zboray, R., Adams, R., & Mosset, J. B. (2018). Monte Carlo simulation of a scintillation detector for spent fuel characterization in a hot cell. Nuclear Engineering and Design, 332, 119-126. https://doi.org/10.1016/j.nucengdes.2018.03.033
Effect of non-uniform reactor cooling on fracture and constraint of a reactor pressure vessel
Qian, G., Niffenegger, M., Sharabi, M., & Lafferty, N. (2018). Effect of non-uniform reactor cooling on fracture and constraint of a reactor pressure vessel. Fatigue and Fracture of Engineering Materials and Structures, 41(7), 1559-1575. https://doi.org/10.1111/ffe.12796
800 fps neutron radiography of air-water two-phase flow
Zboray, R., & Trtik, P. (2018). 800 fps neutron radiography of air-water two-phase flow. MethodsX, 5, 96-102. https://doi.org/10.1016/j.mex.2018.01.008
Development of neutron and X-ray imaging techniques for nuclear fuel bundle optimization
Zboray, R., Bolesch, C., & Prasser, H. M. (2018). Development of neutron and X-ray imaging techniques for nuclear fuel bundle optimization. Nuclear Engineering and Design, 336, 24-33. https://doi.org/10.1016/j.nucengdes.2017.04.035
Gamma radiography and tomography with a CCD camera and Co-60 source
Adams, R., & Zboray, R. (2017). Gamma radiography and tomography with a CCD camera and Co-60 source. Applied Radiation and Isotopes, 127, 82-86. https://doi.org/10.1016/j.apradiso.2017.05.011
An exploratory work on the use of a Lagrangian-Eulerian model for simulating heat transfer of subchannels under reflooding conditions
Badillo, A., & Andreani, M. (2017). An exploratory work on the use of a Lagrangian-Eulerian model for simulating heat transfer of subchannels under reflooding conditions. Nuclear Engineering and Design, 321, 156-172. https://doi.org/10.1016/j.nucengdes.2016.11.031
A three-dimensional, immersed boundary, finite volume method for the simulation of incompressible heat transfer flows around complex geometries
Badreddine, H., Sato, Y., Berger, M., & Ničeno, B. (2017). A three-dimensional, immersed boundary, finite volume method for the simulation of incompressible heat transfer flows around complex geometries. International Journal of Chemical Engineering, 2017, 1726519 (14 pp.). https://doi.org/10.1155/2017/1726519
Potentials, costs and environmental assessment of electricity generation technologies
Bauer, C., Hirschberg, S., Bäuerle, Y., Biollaz, S., Calbry-Muzyka, A., Cox, B., … Tran, M. Q. (2017). Potentials, costs and environmental assessment of electricity generation technologies. Paul Scherrer Institut.
Severe accident code-to-code comparison for two accident scenarios in a spent fuel pool
Coindreau, O., Jäckel, B., Rocchi, F., Alcaro, F., Angelova, D., Bandini, G., … Zhabin, O. (2017). Severe accident code-to-code comparison for two accident scenarios in a spent fuel pool (p. (12 pp.). Presented at the 8th European review meeting on severe accident research (ERMSAR 2017). .
A large eddy simulation of turbulent particle-laden flow inside a cubical differentially heated cavity
Dehbi, A., Kalilainen, J., Lind, T., & Auvinen, A. (2017). A large eddy simulation of turbulent particle-laden flow inside a cubical differentially heated cavity. Journal of Aerosol Science, 103, 67-82. https://doi.org/10.1016/j.jaerosci.2016.10.003
The influence of thermal radiation on the free convection inside enclosures
Dehbi, A., Kelm, S., Kalilainen, J., & Mueller, H. (2017). The influence of thermal radiation on the free convection inside enclosures (p. 405 (12 pp.). Presented at the 8th European review meeting on severe accident research (ERMSAR 2017). .
 

Pages