Number of simulated fuel rods:5
Pressure min:6.9 MPa
Pressure max:6.9 MPa
Temperature min:385 °C
Temperature max:385 °C
Keywords General:
Keywords Core:
Keywords Others:
J. A. Findlay and G. L. Sozzi, BWR Refill-Reflood Program-Model Qualification Task Plan, NP-1527, NUREG/CR-1899, GEAP-24898, August 1981
G. L. Sozzi and W. A. Sutherland, Critical Flow of Saturated and Subcooled Water at High Pressure, NED0-13418, 1975
http://www.iaea.org/inis/collection/NCLCollectionStore/_Public/12/577/12577707.pdf
Md. Alamgir, BWR Refill-Reflood Program Task 4.8- TRAC-BWR Model Qualification for BWR Safety Analysis- Final Report, NUREG/CR-2571, EPRI NP-2377, GEAP-22049, 1983
BWR Slowdown/Emergency Core Cooling Program 64-Rod Bundle Slowdown Heat Transfer (8X8BDHT), Final Report, GEAP-NUREG-23977, 1978
https://inis.iaea.org/search/searchsinglerecord.aspx?recordsFor=SingleRecord&RN=11499817
BWR Large Break Simulation Tests- BWR Slowdown/Emergency Core Cooling Program, NUREG/CR-2229, EPRI NP-1783, GEAP-24962, 1981
https://inis.iaea.org/search/searchsinglerecord.aspx?recordsFor=SingleRecord&RN=14727956
Loss-of-Coolant Accident and Emergency Core Cooling Models for General Electric Boiling Water Reactors, NED0-1 0329, 1971
Relevance | Phenomenon |
---|---|
Break Flow | |
Entrainment and Deentainment | |
Flashing | |
Phase separation |