Dong Duo

Chinese nuclear heating test reactor and demonstration plant

Abstract In this report the importance of nuclear district heating is discussed. From the viewpoint of environmental protection, uses of energy resources and transport, the development of nuclear heating in China is necessary. The development program of district nuclear heating in China is given in the report. At the time being, commissioning of the 5 MW Test Heating Reactor is going on. A 200 MWt Demonstration Plant will be built. In this report, the main characteristics of these reactors are given. It shows this type of reactor has a high inherent safety. Further the report points out that for this type of reactor the stability is very important. Some experimental results of the driving facility are included in the report.

Studies on the performance of the hydraulic control rod drive for the NHR-200

Theoretical analysis and experimental study on the steady state property of the hydraulic control rod drive mechanism for the 200 MW nuclear heating reactor have been carried out in depth. The minimum and maximum holding flow in steady state and their changes along with temperature were identified, and the relationship between the steady state property and the design data of the control rod drive mechanism was analyzed too. A fine agreement between the analysis results and measured data has been achieved.

Study on step-up characteristic of hydraulic control rod driving system

This paper illustrates the work principle of the hydraulic control rod driving system (HCRDS) and the operation of step-up process. As well as the dynamic characteristic of step-up process with the study of experimental results, it also analyzes the influencing parameters of the step-up process, such as holding-flow rate, lift delay time and pressure in front of combined valve, etc. The initial theoretical model of step-up process of HCRDS has been established on the basis of rational analysis, simplification and hypothesis. The calculation result of the theoretical model approximately coincides with the experimental result, which lays a solid foundation for the auxiliary mechanism analysis of HCRDS.

Experimental study and operation experiences of the 5 MW Nuclear Heating Reactor

Abstract The 5 MW nuclear heating reactor (NHR-5) is the first vessel type heating reactor in operation. Since November 1989 the 5 MW nuclear heating reactor has operated successfully for three years during the winter. A series of experiments and operation tests were carried out during the commissioning and operation periods. The main results of the experiments are given in this paper. It has been shown that the NHR-5 possesses excellent safety characteristics and a high operation availability.

Spent fuel storage in pressure vessel for a nuclear heating reactor

In large reactors, the fuel handling including spent fuel storage is solved by deep, lined channels and a spent fuel pool. Since the cores and pressure vessels of heating reactors are largely due to their low volumetric power density and integrated arrangement of primary heat exchangers, in-vessel storage will be a most attractive solution to achieve the economic aim by simplifying a classic refueling scheme. Furthermore, the experiences of long term fuel storage at higher temperatures and reaching very close to the active core will be gained by investigating the effects and data of fuel bundles before discharging. This paper presents an in-vessel storage scheme developed by INET (Institute of Nuclear Energy Technology).

Pre-project study of a nuclear desalination demonstration plant for Tan-Tan, Morocco

Abstract A pre-project study of a nuclear desalination demonstration plant has been jointly carried out by Morocco and China for Tan-Tan, Morocco under the support of the International Atomic Energy Agency. The plant will produce 8000 m 3 per day of potable water using a 10 MWth nuclear heating reactor developed by China coupled to a high-temperature multi-effect distillation process. This paper presents the outline of the Tan-Tan project, including the main features of the reactor and desalination plant, siting and environmental impact assessment, and economic evaluation.

Containment for the low temperature district nuclear-heating reactor

Abstract An integral arrangement is adopted for the Low Temperature District Nuclear-Heating Reactor. The primary heat exchangers, control rod drives and spent fuel elements are put in the reactor pressure vessel together with the reactor core. The primary coolant flows in natural circulation through the reactor core and the primary heat exchangers. The primary coolant pipes penetrating the wall of the reactor pressure vessel are all of small diameters. The reactor vessel constitutes the main part of the pressure boundary of the primary coolant. Therefore a small sized metallic containment closed to the wall of the reactor vessel can be used for the reactor. Design principles and functions of the containment are the same as for the containment of a PWR. But the adoption of a small sized containment brings about some benefits such as a short period of manufacturing, relatively low cost, and ease for sealing. A loss of primary coolant accident would not be happened during a rupture accident of the primary coolant pressure boundary inside the containment owing to its intrinsic safety.