Number of simulated fuel rods:9
Pressure min:0.1 MPa
Pressure max:1 MPa
Power min:170 kW
Power max:170 kW
Keywords General:
Keywords Core:
Keywords Steam Separator:
Keywords Others:
M. Sencar and N. Aksan: "Independent Assessment of RELAP5/Mod 3 with Lehigh University and PSl-NEPTUN Reflooding Tests" Code Assessment and Maintenance Program Meeting, PSI-Switzerland June 1992.
Two-phase 3x3 rod bundle test facility for post-critical heat flux boiling, NUREG I CR - 3849, 1984 (ACC #: 8407060340 /06/30/1984)
Thermodynamic noneqilibrium in post-critical heat flux boiling in a rod bundle : 1. Description of experiments and sample results (NUREG/CR-5095, ACC #: 88071100494, 1988)
Thermodynamic noneqilibrium in post-critical heat flux boiling in a rod bundle : 2.retreating Quench Front tests (ACC # : 8807110476, 1988)
Thermodynamic noneqilibrium in post-critical heat flux boiling in a rod bundle : 3.stabilized Quench Front tests (ACC #: 8807110524, 1988)
https://inis.iaea.org/search/searchsinglerecord.aspx?recordsFor=SingleRecord&RN=20008682
Thermodynamic noneqilibrium in post-critical heat flux boiling in a rod bundle : 4. Advancing Quench Front Tests (ACC #: 8807110530,1988)
https://inis.iaea.org/search/searchsinglerecord.aspx?recordsFor=SingleRecord&RN=19106264
Int. J. Heat and Mass Transfer, Vol. 31. No. 10. pp 2091 - 2100, Convective film boiling in a rod bundle: axial variation of nonequilibrium evaporation rates, 1988
https://www.sciencedirect.com/science/article/pii/0017931088901196
Relevance | Phenomenon |
---|---|
Heat Transfer : Core | |
Heat Transfer : SG | |
Quench Phenomena |