48 results about "Research reactor" patented technology

The invention belongs to the field of environment protection, and in particular relates to an optimization design method of an anaerobic continuous flow agitator bath type biological hydrogen production reactor. The method comprises the following steps: researching reactor internal flow field characteristics of different types of stirring paddles under the conditions of different paddle-bath diameter ratios and different agitating speeds and influence on hydrogen production process, by using a numerical simulation software based on computational fluid mechanics technology; obtaining detailed flow field information, such as velocity field, turbulence energy and dissipation rate thereof, biogas integration rate and shearing rate distribution by adopting a two-phase flow model, and analyzing and comparing different flow field information obtained through simulation according to influence on hydrogen production process by the various flow field information, thereby determining an optimal stirring paddle style and agitating speed combination, and providing an effective method for the optimization design of the agitator bath reactor. The optimization design method of the anaerobic continuous flow agitator bath biological hydrogen production reactor is mature in technology, avoids the blindness of hydraulic design of the reactor using an empirical or semiempirical association method, and has the advantages of being visual in optimization cycle effect and short in optimization cycle, saving cost, and the like.

An instrumented capsule for nuclear fuel irradiation tests in research reactors. The capsule includes an outer shell; a rod tip assembly assembled to a lower end plate of the shell, thus absorbing impact; fuel rod assemblies supported in the shell by means of support tubes and housing therein sintered fuel bodies and in-capsule instruments, such as thermocouples and self-powered neutron detectors (SPND); a protective tube connected to the upper end plate and protecting instrument control cables; and a guide pipe connected to the inclined extension part of a junction tree and guiding the instrument control cables to a control unit provided outside the reactor. The capsule further includes upper and lower end caps provided around the upper and lower ends of the shell; and a lower stopper and an upper stopper fitted over the protective tube to be supported in the upper portion of the irradiation hole of the reactor and to be locked to the locking clamp provided at the upper portion of the chimney of the reactor, respectively. The capsule is used to measure in real time the properties of nuclear fuels irradiated in the reactor during a nuclear fuel irradiation test, thus providing nuclear fuel irradiation test data required for the design of nuclear fuels and the determination of in-pile performance and structural integrity of the nuclear fuels.

The invention discloses a modularized control rod driving system and a modularized control rod driving method for a horizontal reactor core structure. The invention provides the modularized control rod driving system which is used for a research reactor of the horizontal reactor core structure and has a passive shutdown function; a ball screw-nut structure is used for accurately controlling the position and the movement speed of a control rod assembly and considers experiment functions of the research reactor. The system comprises a horizontal reactor core passive shutdown mechanism, a modularized control rod driving device and a control rod driving system rack, wherein the horizontal reactor core passive shutdown mechanism is used for driving the control rod assembly by a traction counter weight, a traction steel wire and a pulley block to rapidly and horizontally move to be inserted into a horizontal reactor core; the modularized control rod driving device is high in integration degree, simple and convenient to maintain and reliable in performance; the control rod driving system rack is used for determining the position of the modularized control rod driving device in the reactor core and the height of the traction counter weight.

The present invention relates to a multi-core fuel rod for research reactor and, more particularly, to a multi-core fuel rod for research reactor in which monolithic fuel cores made of uranium-molybdenum alloy are disposed in an aluminum matrix in a multi-core form. The multi-core fuel rod in accordance with the present invention provides a minimized contact surface area between nuclear fuel and aluminum, and reduces the formation of pores and swelling by restraining formation of reaction layer to avoid excessive reaction between the fuel and aluminum. Therefore, improved stability of nuclear fuel can be obtained by minimizing temperature rise as well as achieving high density and thermal conductivity of the fuel.

The invention relates to a fuzzy control-based research reactor power automatic adjustment method. The method comprises the following steps: establishing a coordinate system by taking a reactor powermultiple period and a reactor power deviation percentage as horizontal and vertical coordinates respectively, dividing the reactor power multiple period and the reactor power deviation percentage intoa plurality of intervals, and setting different target rod speeds of an adjusting rod for intersection areas of different intervals; calculating a reactor power multiple period and a reactor power deviation percentage according to the current reactor power; and determining an area to which the reactor power multiple period and the reactor power deviation percentage belong in the coordinate systemaccording to a calculation result, and driving an adjusting rod according to a target rod speed set in the area. The method is simple and effective, the operation safety of a research reactor is ensured, and the long-term stable power operation of the research reactor is also ensured.

The invention discloses an irradiation target containing Np-237 for producing Pu-238 in a research reactor, comprising a target cylinder and an upper end and a lower end arranged at both ends of the target cylinder, the target cylinder is provided with a cooling function The tall target to be irradiated has good cooling effect and is suitable for the production of Pu‑238 by irradiation of research reactors. The irradiation target of the present invention can irradiate Pu-238, and has high conversion rate and good safety.

An instrumented capsule for nuclear fuel irradiation tests in research reactors includes an outer shell; a rod tip assembly assembled to a lower end plate of the shell, thus absorbing impact; fuel rod assemblies supported in the shell by means of support tubes and housing therein, sintered fuel bodies and in-capsule instruments, such as thermocouples and self-powered neutron detectors (SPND); a protective tube connected to the upper end plate and protecting instrument control cables; and a guide pipe connected to the inclined extension part of a junction tree and guiding the instrument control cables to a control unit provided outside the reactor.

The invention belongs to the field of nuclear radiation, and particularly relates to a method for producing carrier-free < 99 > Mo by a heavy water reactor. At present, global < 99 > Mo is mainly carrier-free < 99 > Mo produced by a research reactor through fission, production of carrier < 99 > Mo by using a heavy water reactor has been developed and utilized internationally, and an example for producing carrier-free < 99 > Mo by using a commercial heavy water reactor has not been seen up to now. By means of the method, large-scale stable production and supply of < 99 > Mo are achieved through the heavy water reactor, and the produced < 99 > Mo is mainly applied to the field of nuclear medicine diagnosis. The method comprises the following steps: 1, confirming loading conditions; 2, determining a loading position; 3, the target piece is put into a pile; step 4, carrying out in-pile irradiation; and 5, discharging the target from the reactor core. On the premise that safe operation of the reactor is not affected and fuel loss is reduced as much as possible, the carrier-free < 99 > Mo is produced through irradiation of the heavy water reactor, and the requirement of the nuclear medicine field for < 99 > Mo is met.

The invention discloses a radiation supervision device for a core container of a high-flux research reactor, which comprises a lifting ring (1), a sample supporting body (2) and a bottom grid plate (3), and is characterized in that the inside of the sample supporting body (2) is provided with a small-sized CT sample, a tensile sample and a temperature monitor. The invention provides the radiationsupervision device which is suitable for the core container of the research reactor and has a simple structure, small volume and reactor-following monitoring.

The present invention relates to a research reactor power automatic adjustment method based on fuzzy control. The method takes the reactor power doubling period and the reactor power deviation percentage as the abscissa and ordinate respectively, establishes a coordinate system, and takes the reactor power doubling period and the reactor power deviation percentage Divide it into several intervals, set different target rod speeds for the adjustment rods for the intersecting areas of different intervals; calculate the reactor power doubling period and reactor power deviation percentage according to the current reactor power; determine the position in the coordinate system according to the calculation results area, the adjusting rod is driven according to the target rod speed set in this area. The method is simple and effective, which not only ensures the operational safety of the research reactor, but also ensures the long-term stable power operation of the research reactor.

The invention discloses a metallic fast reactor fuel element irradiation test device. The device can be used for carrying out neutron irradiation test on metallic fast reactor fuel in a thermal spectrum research reactor and has the functions of neutron spectrum hardening, metallic fuel irradiation temperature control, fuel element heat release power measurement and the like. The device comprises aprotection tube, a cadmium tube, an irradiation test piece, a related gas pipeline, a thermocouple and the like. According to the device, a cadmium metal layer is adopted to absorb thermal neutrons to reduce the thermal neutron flux rate in the device, so that the neutron energy spectrum of a test fuel element is close to that of a fast neutron reactor; and the temperature difference is established between air gaps and a liquid metal layer outside a fuel rod, and the gas components in the air gaps in each irradiation part are independently adjusted, so that the temperature of fuel core bodiesin different irradiation parts are controlled within a required temperature range.

The invention discloses a multipurpose heat pipe stack prototype, which belongs to the technical field of reactor experimental devices, and comprises: a hexagonal matrix for simulating the solid core of a heat pipe stack; a plurality of heating rods inserted in the hexagonal matrix , for simulating reactor fuel bundles; Stirling thermoelectric converters, for simulating dynamic thermoelectric conversion processes; silent thermoelectric converters, for simulating static thermoelectric conversion processes; multiple high-temperature alkali metal heat pipes, for simulating the realization of reactor Core cooling and energy transmission process; pressure-bearing protective shell, covering the outside of the hexagonal matrix, multiple heating rods, multiple high-temperature alkali metal heat pipes, Stirling thermoelectric converters and silent thermoelectric converters. The invention can verify the feasibility of multi-purpose heat pipe reactor nuclear power technology, and can be used to study the response of heat pipe operation characteristics and energy conversion device operation characteristics when the power of the core changes, and to study the coupling characteristics of the core-heat pipe-energy conversion device.