Advanced neutron source reactor thermal-hydraulic test loop facility description

FY 1993 progress report on the ANS thermal-hydraulic test loop operation and results

“…A detailed description of the experimental procedures and operation is given by Felde, Yoder, and Sknycke (1992) and by Felde et al (1994). Prior to installation of the test channel assembly into the loop, the channel surface undergoes a surface treatment procedure similar to that used for fuel elements in the High Flux Isotope Reactor at ORNL and expected to be used for the ANSR fuel elements.…”

“…4. A detailed description of the test facility is given by Felde, Yoder, and Skrzycke (1992) and by Felde et al (1994). In the design process, special consideration was given to include the proper pump, test section bypass configuration, and system valving and piping to allow operation of the system in either stiff or soft modes, as discussed earlier.…”

“…A condensed version of the material presented in this report was published by Siman-Tov et al (1993, March 1995, and April 1995. The reader should also refer to an earlier progress report (Siman-Tov et al 1994) and for a general description of the THTL facility, to Felde et al (1994).…”

Research and Development of Multiphysics Models in Support of the Conversion of the High Flux Isotope Reactor to Low Enriched Uranium Fuel

“…During the design process for the ANSR, many experiments were performed in order to establish a safety basis for the reactor operations and to better quantify the design requirements. Flow tests measuring thermal characteristics of the fuel plates were performed that were designed to measure the heat transfer capabilities of the design [104][105][106][107]. Another set of experiments were performed to test the deflection caused by the pressure differentials from the coolant flow [101,63,102,59,103,108,109,110].…”

Advanced Neutron Source (ANS) Project progress report, FY 1994

“…The THTL facility was designed and built to provide known T/H conditions for a simulated full-length coolant subchannel of the ANSR core, thus facilitating experimental determination of FE and critical heat flux (CHF) thermal limits under expected operational conditions. Detailed descriptions of the test facility and the test section design are given in Felde et al (1994) and in last year's ANS annual report (Selby, Hamngton, and Peretz 1994).…”