LOFT: a nuclear plant providing realistic answers to PWR licensing issues

This paper discusses the role the Loss-of-Fluid Test (LOFT) Experimental Program has played and will play in addressing licensing issues of interest to the US Nuclear Regulatory Commission (NRC), nuclear steam supply system vendors, and utility power companies. The LOFT facility is an operating, prototypically scaled pressurized water reactor (PWR) system in which experiments are performed that characterize conditions for postulated accidents in a commercial PWR. The accident conditions imposed have not caused damage to the LOFT system, and the system has been succesfully stabilized and recovered in each instance. Data from these experiments have provided and will continue to provide realistic answers to PWR licensing issues both before and after the accident at Three Mile Island (TMI)

Transient three-dimensional thermal-hydraulic analysis of nuclear reactor fuel rod arrays: general equations and numerical scheme

A mathematical model and a numerical solution scheme for thermal- hydraulic analysis of fuel rod arrays are given. The model alleviates the two major deficiencies associated with existing rod array analysis models, that of a correct transverse momentum equation and the capability of handling reversing and circulatory flows. Possible applications of the model include steady state and transient subchannel calculations as well as analysis of flows in heat exchangers, other engineering equipment, and porous media. (auth

Test of the EG and G two-phase mass flow rate instrumentation at Kernforschungszentrum Karlsruhe Data report vol. 1: Test results from LOFT production DTT and a LOFT type gamma densitometer

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