Title :
Thermal-hydraulic analysis for the upgraded MIT nuclear research reactor
Author :
Hu, Lin Wen ; Bernard, John A.
Author_Institution :
MIT, Cambridge, MA, USA
Abstract :
The thermal-hydraulic analysis performed for a planned upgrade of the MIT Research Reactor from 5 to 6-7 MW using the existing heat removal equipment is reported. This upgrade is one of several options under consideration for the relicensing of the MIT Research Reactor in 1999. Included in this paper is a description of the calculations of thermal-hydraulic limits which include limiting safety system settings (LSSS) and safety limits (SL). The LSSS and SL were respectively chosen to avoid onset of nucleate boiling and flow instability during steady-state operation. These analyses were performed using the MULti-CHannel-II or MULCH-II code which was developed and benchmarked at MIT for design and safety analysis of the MIT Research Reactor
Keywords :
boiling; fission reactor cooling; fission reactor safety; fission research reactors; flow instability; MULCH-II code; flow instability; heat removal equipment; limiting safety system settings; nucleate boiling; steady-state operation; thermal-hydraulic analysis; thermal-hydraulic limits; upgraded MIT nuclear research reactor; Educational technology; Fuels; Inductors; Licenses; Performance analysis; Safety; Senior members; Steady-state; Transient analysis; Valves;
Conference_Titel :
Nuclear Science Symposium, 1997. IEEE
Conference_Location :
Albuquerque, NM
Print_ISBN :
0-7803-4258-5
DOI :
10.1109/NSSMIC.1997.670451
