The Advanced Neutron Source Thermal Hydraulic Test Loop
- Oak Ridge National Lab., TN (United States)
- Tennessee Univ., Knoxville, TN (United States). Dept. of Mechanical Engineering
The Advanced Neutron Source (ANS) Thermal Hydraulic Test Loop has been designed to provide known thermal-hydraulic conditions to a test section which simulates a full-length aluminum coolant subchannel of the ANS reactor core. Tests in this facility will provide both single- and two-phase thermal-hydraulic information. The specific phenomena that are to be examined are (1) single-phase heat transfer coefficients and friction factors, (2) the point of incipient boiling, (3) nucleate boiling heat transfer coefficients, (4) two-phase pressure drop characteristics in the nucleate boiling regime, (5) flow instability limits, and (6) critical heat flux limits. A Moyno ``near`` positive displacement type primary group with a 4 MPa differential head is capable of providing up to 35 m/s flow through the narrow channel test section. Two 12-volt dc power supplies, operated in parallel, with 40 kA total current capacity provide direct resistance heating to the test channel. A primary heat exchanger is designed to remove up to 410 kw. Data acquisition for the loop is through two PC-based systems, one of which is a fast data acquisition system capable of measuring up to 100,000 samples/s. As an aid in test design and analysis, an analytical model has been developed to predict the thermal hydraulic response of the test loop under transient conditions.
- Research Organization:
- Oak Ridge National Lab., TN (United States)
- Sponsoring Organization:
- USDOE, Washington, DC (United States)
- DOE Contract Number:
- AC05-84OR21400
- OSTI ID:
- 10137700
- Report Number(s):
- CONF-920538-11; ON: DE92011105
- Resource Relation:
- Conference: 8. power plant dynamics, control and testing symposium,Knoxville, TN (United States),27-29 May 1992; Other Information: PBD: [1992]
- Country of Publication:
- United States
- Language:
- English
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