[en] Palladium/silver films with Ag content of (27.5 +- 0.3) at.% and a thickness of about 8 microns have been made by pulse and multi-layer plating techniques, the substrate of which is a type of 316 stainless steel filter plate. The annealing condition is determined to prepare a palladium/silver alloy film for hydrogen with a homogeneous composition, stable structure and good sticking performance with the substrate. Its permeability and selectivity to hydrogen are examined under 350 degree C. The permeation rate by area is 9.1 times greater than the commercial PdAg25at.% membrane and the selectivity to H₂-He system is up to 500. It could be concluded that the supported Pd/Ag alloy selectively permeated film for hydrogen is suitable to the fuel treatment of fusion-fission hybrid reactor in China

[en] The calculation method and results of the stress failure probability of the fuel element for HTR-10 after irradiation are presented

[en] Ratio control, a new control method for nuclear steam supply system (NSSS) in high temperature nuclear power plant, is introduced by the control system design for NSSS in 10 MW high temperature gas cooled test reactor (HTR-10). The simulation results show that the ratio control makes the helium temperature of the exit and the entrance to the core change in an allowable range: the temperature of primary steam keeps at the given value and the pressure change at the primary loop is no more than 10% of rated value. The capability for heat transfer and heat removal is uninfluenced. So it is not necessary to control for the primary loop pressure. The design for control system is simplified

[en] Sol-Gel method is used to prepare Li₂ZrO₃ microsphere. The microspheres have a diameter of 0.4∼1.0 mm, density of 80∼90% T.D., specific surface of 18∼32 m²/g, crushing strength of 1∼3 kg/microsphere and smooth surface. This technique could be used to fabricate microsphere of other materials

[en] When a nuclear power station operates, valves are the devices which easily cause an accident. In order to guarantee the safety of nuclear station, reliable valves must be chosen. There are more than 10 varieties, over 300 in quantity of helium valves included in 10 MW High Temperature Helium Cooled Test Reactor (termed HTR-10). These valves are not only widely used as pressure-resistant devices, but also are connected with a large number of systems in HTR-10. So they play an important role in ensuring normal operation and shut-down in safety of HTR-10. The authors present the requirements of helium valves in HTR-10, and introduce the design, inspection and test of nuclear-class helium valves in HTR-10

[en] In order to research the physics characters of pebble bed HTGR, a complete computer simulation method and a correspondent physical computation program system have been developed. The special features of the method are as follows: the double heterogeneity of a fuel element with coated particles grain structure and the motion behaviour of a fuel ball are considered; the complex fuel manage in pile and out pile can be treated; the top cavity for loading the fuel pebbles is considered; the buckling feedback in the spectral calculation is introduced; the direct coupling between physics and thermal hydraulics is made. The method and code have been used in HTR-10 physics design

[en] First in-pile tririum production apparatus of China is introduced. Main parts of the apparatus and its characters are showed. Operation Outline of the apparatus and results of the tritium release experiment are briefly described. Utilization of the apparatus in tritium production research of fusion-fission hybrid reactor blanket and its future are reviewed

[en] Taking ²³⁸U or the mixture of ²³⁸U and ²³⁹Pu as the blanket fuel, and neutron from inertia confinement fusion (ICF) as the driving source, and presuming that the inertia confinement fusion does not reach an equivalence of energy loss and gain, the fusion/fission hybrid reactor system was studied conceptually. A conception that the energy gain could be improved through using the ²³⁹Pu as a combustion-supporting material has been developed. Since the ²³⁹Pu has been introduced, the neutron flux in blanket is raised and the Pu production from ²³⁸U and Pu's burnup is accelerated. Therefore, the energy is released from the burnup of ²³'8U and very little amount of Pu rather than large amount of Pu, and the energy gain in the blanket reaches 30 or more. From all the study above, a possible way of early stage application of ICF and the continuous development of fission energy resource by using ²³⁸U as fuel perhaps could be provided

[en] Most High Temperature Gas-Cooled Reactor (HTR) systems are significantly under-moderated for economic reasons, so that accidental water or steam ingress, e.g. due to the rupture of a steam generator tube, can increase the reactivity of the system significantly and decrease the worth of the control rods. These will affect the safety of the system. Water ingress experiments with water are not feasible in most of HTR core configurations because of the difficulties in obtaining precisely controlled amounts of water in the core and in later removing water from the graphite and safety considerations. Water ingress effects can be studied by inserting the polyethylene (CH₂) plastic rods into the core. Inserting different quantities of polyethylene plastic rods with different diameters in the core can simulate different amounts of water ingress

[en] The authors briefly introduce the functions, design parameters, system flowsheet, main equipment and design features of 10 MW HTR-TM fuel handling system