[en] The main design and operating parameters for the 10 MW high temperature gas-cooled reactor (HTR-10) primary loop pressure boundary system are introduced in this paper. The component installations and the pneumatic and tightness test are also described, including the objectives and methods. The leakage rate test results are analyzed to show that the results meet the design requirements and have enough safety redundancy

[en] LTHR-200 is a low temperature district-heating reactor. It adopts double-shell design pressure vessel and metal containment. Because of the safety and structural features of the reactor, the in-service inspection of the pressure vessel can be simplified greatly. LTHR-200 is an integrated arrangement. Both its core components and the main heat exchangers are contained in the reactor pressure vessel. The coolant of the main loop is run by a full-power natural circulation and there need no main pumps and pipes. Thus, the reactor pressure vessel constitutes the pressure boundary of the reactor's main loop coolant. In regard to these features, a small-sized containment is designed for the reactor. The metal safety container with a small volume is placed closely around the reactor pressure vessel. Outside the metal containment, there is a large reinforced concrete construction for the reactor. Their main operation and design parameters are as follows: The pressure vessel: operation pressure = 2.4 MPa; design pressure = 3.0 MPa; design temperature = 250 deg C; 40 year fast neutron (E>1MeV) fluence in the belt-line region = < 10E16n/cm; internal diameter = 5000 mm; material SA516-70; shell thickness 65 mm; The metal containment: maximum operation pressure = 1.8 MPa; design pressure = 1.8 MPa; design temperature = 250 deg. C; upper internal diameter 7000 mm; lower internal diameter = 5600 mm; material = SA516-70; shell thickness, upper part = 80 mm; lower part = 50 mm. All penetrating pipes through the pressure vessel are located at the top penetration section of the shell. All the internal diameters of penetrating pipes are less than 50 mm. Inside and outside the metal containment wall respectively, isolating valves are connected to the reactor coolant pipe which passes through the containment. These two isolating valves use different driving methods. Every penetrating part of the reactor construction uses a proper form of structure according to safety requirements. (author)

[en] This article describes the structural design requirements, structural arrangement and structural features of the ceramic and metallic internals of the 10 MW high-temperature gas-cooled reactor-test module (HTR-10). The graphite properties used in the ceramic internals are provided, along with the results of an operating stress analysis of the graphite components and the metallic components. Satisfactory results were obtained for the machining and installation of the ceramic components and the stress analysis of the graphite and metallic components of HTR-10

[en] The Design and analysis of the pressure vessel and containment were done according to correspending Chinese codes, standards and ASME code. The overall arangement and the structural features of both the pressure vessel and the containment are described. Their design, calculations, stress analysis and strength assessment are briefly explained as well

[en] The flanges are the key structures of the HTR-10 pressure vessel and play an important role during its service life. They are bolt-connected and the sealing components consists of a metallic O-ring and a welded Ω-ring. An elastic-plastic nonlinear analysis is considered to evaluate the stress and deformation of flanges. In order to simulate the processes of pre-tightening and pressurizing of HTR-10 pressure vessel, the loads are added by multi-step skill. The MSC MARC 2000 is employed and an axisymmetric finite element model is used. The analysis results show that the flanges can meet the strength requirement and the O-ring and the Ω-ring seal the HTR-10 pressure vessel very well during both the pre-tightening and pressurizing

[en] Formaldehyde is a well-known indoor air pollutant that is regulated by authorities worldwide. Formaldehyde has adverse health effects in humans, especially as a sensory irritant to the eyes and to the upper air way, and more importantly, it is a known carcinogen. Adsorption by carbon adsorbents is an old, but indispensable cleaning technology for combating indoor formaldehyde. In this study, we report isotherms and 2D-density distributions by conducting comprehensive Monte Carlo simulation. The effects of the functional group and pore size were investigated. We found that formaldehyde has a different response when the number of functional group and pore size change from that of water. Therefore, by tuning pore size and functionalities it may be feasible to produce real materials that retain effective capture of formaldehyde but which avoid pore blocking by water based on the differences in adsorption properties between water and formaldehyde. (paper)

[en] SA516-70 plate has the characteristics of moderate intensity, high tenacity and well welding property. The authors have manufactured the 10 MW High Temperature Gas-cooled Reactor pressure vessel with SA516-70 plate. The mechanical behaviour of SA516-70 is fit for the design requirement and it has been validated by the hydrostatic test

[en] When nuclear class I helium safety relief valves are tested in the safety relief test loop HTR-10 (10 MW High Temperature Gas Cooled Reactor), in order to prevent particles in flow medium from damaging the sealing surface of the safety valves, the flow medium has to be filtrated. For this, a high efficient filter was installed in the upstream of the safety valves. This paper presents the design and manufacture process of the filter pressure vessel. The hydraulic pressure test and air pressure test results have shown that the pressure vessel satisfies the design requirements. (authors)

[en] In this paper, the following two aspects are analyzed with thermal-elastic finite element method: - The stress intensity and deformation of some significant parts of LTHR-200 pressure vessel are calculated. - The influence of LTHR-200 pressure vessel structure on sealing behavior of main flanges is analyzed in the condition of start, shutdown and operation. (author)

[en] The hydraulic pressure test of 10 MW High Temperature Gas-cooled Reactor (HTR-10) pressure vessel was successfully performed according to the requirement of the section NB-6200, ASME III code. The test requirement, the test results and the test evaluations are described in detail. The test tension was effectively and rationally done through an hydraulic tensioner, which was developed at institute of nuclear energy technology of Tsinghua University. The strain and deformation of the HTR-10 pressure vessel were also measured