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Cheung, Y.K.; Parameswaran, V.; Shaug, J.C.
General Electric Co., San Jose, CA (USA). Nuclear Fuel and Special Projects Div1983
General Electric Co., San Jose, CA (USA). Nuclear Fuel and Special Projects Div1983
AbstractAbstract
[en] TRAC (Transient Reactor Analysis Code) is a computer code for best-estimate analysis for the thermal hydraulic conditions in a reactor system. The development and assessment of the BWR component models developed under the Refill/Reflood Program that are necessary to structure a BWR-version of TRAC are described in this report. These component models are the jet pump, steam separator, steam dryer, two-phase level tracking model, and upper-plenum mixing model. These models have been implemented into TRAC-B02. Also a single-channel option has been developed for individual fuel-channel analysis following a system-response calculation
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Sep 1983; 117 p; EPRI-NP--2376; GEAP--22052; Available from NTIS, PC A06/MF A01 - GPO $5.00 as DE84900137
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Numerical Data
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