[en] The refrigeration test of 5 MW Nuclear Heating Reactor Refrigeration (NHR-R) system is made according to its great significance. The test proves that NHR-R possesses a series of advantages, such as stable heating parameters, fine characteristics of following and self-stability to the changes of external load. The success of this nuclear refrigeration test provides valuable technical data and operating experiences for the design, construction and operation of the business NHR-R engineering. Finally, two comprehensive application plans of NHR-R system are introduced. 1) Heating-electricity cogeneration and refrigeration (steam as heating source); 2) Heating and refrigeration (hot water as heating source)

[en] The Digital-Analog Rod Position Detector consisting of several group transformers and one coding bar is introduced. It is composed of two long opposite and two short secondary coils arranged on longitudinal axis of rod housing and a coding bar possessing a magnetic core and a non-magnetic portion. While the bar passes the secondary coils, their outputs which are inducted by the exciting signal of the primary coil will be changed. By analyzing and processing the varying outputs, the control rod position is gotten. Further, the authors describe the principle of the detector and its experiments. The conclusion shows that the detector has many advantages such as simple construction, excellent reliability and high detection precision and its is able to be used for rod position detection of Nuclear Heating Reactor (NHR)

[en] A new type gripper with no power supply for loading or unloading a fuel assembly into or from the core of low temperature heating reactor is developed and tested. The operating principle, characteristics of structure, designing parameters and remarkable advantages are introduced, ease in operation and reliable. It can be used in other light water reactors for fuel assembly handling operation

[en] The author analyzes in detail the way of thermal cycle for low temperature nuclear heating reactor, and enumerates some power cycles. The characteristics of heating and cooling source in 5 MW, 200 MW, 500 MW nuclear heating reactor thermal-power co-supply, all kind of power cycles have been calculated, analyzed and compared. The result is that the heating source which offered by different nuclear heating reactor, requires the different power cycle to suit for it

[en] Using 5 MW low-temperature heating test reactor as experimental basis, the research of nuclear energy applications, such as heat-electricity co-generation, process steam supply, nuclear refrigeration and nuclear desalination of sea water is introduced. The emphases are in the principles, systems and parameters to realize the items mentioned above. The purpose of the study is to find ways for comprehensive utilization of the nuclear heating reactor at the commercial-scale. Therefore, the nuclear heating reactor could reduce its costs and have advantages to compete with coal-fired plant

[en] The characteristic of primary heat exchanger for 5 MW THR is described. The heat transfer coefficient and resistance coefficient of primary side of primary heat exchanger are given

[en] An experiment of small break of upper plenum joint pipe is described. In the test, the system working parameter on conditions that there is rest power after the reactor being shut down were studied at the heating reactor thermohydraulic test system HRTL-5. The effect to nuclear heating reactor safety under break conditions is given

[en] That there is a certain void content in the core of the 5 MW nuclear heating reactor (NHR-5) under power operation conditions has been inferred by a special experiment. The inference above is verified using COBRA-III C/MIT2 and RETRAN-02 with a highly subcooled boiling calculation model, while average void fraction under the rated condition is 1.06 x 10^-2. Characteristics of highly subcooled void are also investigated. The analysis results are consistent with the experiments of self-regulation and self-stabilization. The analyses also indicate that the reactivity feedback of highly subcooled void has an important influence on various operation transients and accidents of the NHR-5

[en] To increase the utilization effectiveness of nuclear heating reactor, the posibility of refrigeration using LiBr in 5 MW THR is discussed

[en] The main loops of 5 MW nuclear heating reactor and 200 MW nuclear heating reactor are integral natural circulation systems. In case of loss of coolant accident (LOCA), while the water level reaches the upper edge of the inlet of the heat exchanger, flow break occurs. It has influence on cooling core and stability of the main loop. An experiment described in this paper is carried out on the thermohydraulic test system HRTL-5 of the nuclear heating reactor. The position of the break is selected on the lower part of the exchanger. The system pressure is 1.5 MPa, the heating power under the accident is kept 5% or 20% of steady state power. Results show the heated element temperature is not too high and could not be burnout. But the flow oscillation in the primary coolant circuit occurs when the flow breaks completely at the end, which is unfavorable. The whole process of flow oscillation is described and its mechanism is inquired