THERMAL-HYDRAULIC CHARACTERISTICS OF THE FLOW HLMC IN CROSSFLOW TUBES

Authors & Affiliations

Beznosov A.V., Jarmonov M.V., Zudin A.D., Chernysh A.S., Novozhilova O.O.
Nizhny Novgorod State Technical University n.a. R.E. Alekseev, Nizhny Novgorod, Russia

Abstract

At present, in world leading countries, including Russian Federation, significant amount of work done aimed at construction of nuclear power plant with fast reactors cooled with heavy liquid metal coolants, such as lead and lead-bismuth eutectic coolants. Development of such systems requires a great deal of theoretical and experimental work, especially in the field of study of the processes of heat exchange and hydrodynamics of heavy liquid metal coolants. The purpose of this work is to carry out experimental research of heat-exchange characteristics, temperature and velocity fields in high-temperature lead coolant in corridor bundle of heat exchanger pipes at the control and regulation of the oxygen impurity content in the coolant and test bench. This paper contains the description and characteristics of test bench FT-2B and thermophysical assembly with cross flow heat exchange surface. Also, the test program is described. It includes following steps:
a) development of methods for forming and removing lead oxide impurity deposits from the loop and test section walls;
b) experimental calculation of the dependency relation Nu=f(Pe), temperature and velocity fields and flow characteristics of lead coolant, during controlled injection of gas with the values of thermodynamically active oxygen in lead from 10-5 …10-4...100;
c) the same calculations during forming a layer of impurity deposits on the heat exchange surfaces of the test section;
d) revision of the bench and test section conditions.
The results of analysis and experimental studies of the heat exchange characteristics of the experimental heat sink, represented by cross flow in corridor bundle heat exchange tubes bank simulating the conditions of heat exchange from the lead to the wall in the range of operating mode parameters of the designed loop of the reactor plant type BREST at a controlled and regulated oxygen impurity content in the coolant and circuit, as well as feeding into lead coolant circuit gas-air mixture that imitate a possible emergency mode when the accident "intercontour leakage of the steam generator" are provided.
Currently there is no numerical model exists, that would reliably describe the processes of heat transfer in a heavy liquid metal coolant. The results of these experiments can help verify the model created in the future.

Keywords
fast reactor, heavy liquid metal coolant, heat exchange, experimental study, corridor bundle of pipes, cross-flow, intercontour leakage of the steam generator, thermodynamically active oxygen, field of temperature, field of velocity

Article Text (PDF, in Russian)

References

UDC 621.039.534.6 + 621.039.526

Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants", issue 1, 2014