A thermal bridge for improving thermal transfer between a fuel element to a fuel block wherein there is provided a high temperature gas cooled nuclear reactor fuel block comprising a fuel channel and a coolant channel wherein the fuel channel comprises a fuel element, the fuel channel further comprising a thermal bridge thermally linking the fuel element and the fuel channel, wherein the thermal bridge comprises a melting point greater than the working temperature of the fuel block, thereby improving thermal transfer from the fuel element to the fuel block, thereby improving thermal transfer to the coolant channel.

A thermal bridge for improving thermal transfer between a fuel element to a fuel block wherein there is provided a high temperature gas cooled nuclear reactor fuel block comprising a fuel channel and a coolant channel wherein the fuel channel comprises a fuel element, the fuel channel further comprising a thermal bridge thermally linking the fuel element and the fuel channel, wherein the thermal bridge comprises a melting point greater than the working temperature of the fuel block, thereby improving thermal transfer from the fuel element to the fuel block, thereby improving thermal transfer to the coolant channel.

The invention discloses a serial high-temperature gas-cooled reactor nuclear energy system and an operating method thereof. The serial high-temperature gas-cooled reactor nuclear energy system includes a plurality of high-temperature gas-cooled reactors and a serial gas-cooled reactor. The high-temperature gas-cooled reactor includes a first reactor pressure vessel comprising a first reaction chamber for accommodating the first fuel element; a second reactor pressure vessel comprising a second reaction chamber interconnected with the first reaction chamber, allowing the first spent fuel in the first reaction chamber to enter the second reaction chamber. The system of the present invention allows the spent fuel discharged from the high-temperature gas-cooled reactor to be directly reused as fuel for the serial gas-cooled reactor, thereby improving the utilization rate of nuclear fuel and reducing the cost of gas-cooled reactors, which is conducive to the promotion of industrialized application of high-temperature gas-cooled reactors.

The invention discloses a serial high-temperature gas-cooled reactor nuclear energy system and an operating method thereof. The serial high-temperature gas-cooled reactor nuclear energy system includes a plurality of high-temperature gas-cooled reactors and a serial gas-cooled reactor. The high-temperature gas-cooled reactor includes a first reactor pressure vessel comprising a first reaction chamber for accommodating the first fuel element; a second reactor pressure vessel comprising a second reaction chamber interconnected with the first reaction chamber, allowing the first spent fuel in the first reaction chamber to enter the second reaction chamber. The system of the present invention allows the spent fuel discharged from the high-temperature gas-cooled reactor to be directly reused as fuel for the serial gas-cooled reactor, thereby improving the utilization rate of nuclear fuel and reducing the cost of gas-cooled reactors, which is conducive to the promotion of industrialized application of high-temperature gas-cooled reactors.

The present disclosure provides a sample holder assembly for a laser flash apparatus for measuring a thermal conductivity of a pebble-bed, the assembly comprising: a tubular sample container configured to be mounted on a sample carrier tube for the laser flash apparatus, wherein the sample container has open top and bottom; a bottom disc disposed in the sample container to block the open bottom of the sample container and configured for delivering a laser from a laser flash unit of the apparatus to a pebble-bed; the pebble-bed packed on the bottom disc to a predetermined thickness; and a top disc disposed on the pebble-bed and in the sample container to block the open top of the sample container and configured for receiving heat from the pebble-bed to transfer the heat upward.

The present disclosure provides a sample holder assembly for a laser flash apparatus for measuring a thermal conductivity of a pebble-bed, the assembly comprising: a tubular sample container configured to be mounted on a sample carrier tube for the laser flash apparatus, wherein the sample container has open top and bottom; a bottom disc disposed in the sample container to block the open bottom of the sample container and configured for delivering a laser from a laser flash unit of the apparatus to a pebble-bed; the pebble-bed packed on the bottom disc to a predetermined thickness; and a top disc disposed on the pebble-bed and in the sample container to block the open top of the sample container and configured for receiving heat from the pebble-bed to transfer the heat upward.

Apparatus for the production of carbon dioxide from limestone includes a nuclear reactor (10) for generating heat and a rotary kiln (12). The rotary kiln (12) has an inlet (28) for the introduction of limestone and an outlet (30) for the release of carbon dioxide. A heat transfer arrangement is provided for transferring heat from the nuclear reactor (10) to the interior of the rotary kiln (12). The heat transfer arrangement includes feed and return primary conduits (17,18) for passing a heat transfer fluid (14) through the nuclear reactor (10) so that heat may be extracted from the nuclear reactor (10) for transfer to the interior of the rotary kiln (12). Limestone in the rotary kiln (12) is thereby heated to a temperature sufficient for the release of carbon dioxide.

Apparatus for the production of carbon dioxide from limestone includes a nuclear reactor (10) for generating heat and a rotary kiln (12). The rotary kiln (12) has an inlet (28) for the introduction of limestone and an outlet (30) for the release of carbon dioxide. A heat transfer arrangement is provided for transferring heat from the nuclear reactor (10) to the interior of the rotary kiln (12). The heat transfer arrangement includes feed and return primary conduits (17,18) for passing a heat transfer fluid (14) through the nuclear reactor (10) so that heat may be extracted from the nuclear reactor (10) for transfer to the interior of the rotary kiln (12). Limestone in the rotary kiln (12) is thereby heated to a temperature sufficient for the release of carbon dioxide.

A nuclear reactor has an axially stratified fuel bed. The reactor features a reactor shell having a base, a top having an exhaust outlet, and an axis. The axially stratified fuel bed is within the reactor shell, and includes: a first zone configured to operate at a first temperature T1, the first zone comprising a plurality of first fuel particles, each first fuel particle comprising a first radioactive ceramic core and a first ceramic seal coating; and a second zone configured to operate at a second temperature T2, where T2>T1, the second zone comprising a plurality of second fuel particles, each second fuel particle comprising a second radioactive ceramic core and a second ceramic seal coating. A coolant fluid flow path carries a coolant fluid from the base of the reactor to the exhaust outlet, along a flow path passing sequentially through the first zone and the second zone. The first ceramic seal coating has greater stability at T1 than at T2, and the second ceramic seal coating has greater stability at T2 than the first ceramic seal coating.

The present disclosure relates to the technical field of reactor engineering, and particularly, to a nuclear power plant spent fuel negative pressure unloading system, comprising a fuel element transport pipe and a gas transport pipe. The fuel element transport pipe comprises a fuel element output pipe, a fuel element lifting pipe, and a fuel element unloading pipe connected in series. The fuel element unloading pipe is arranged obliquely downward in the direction of fuel element movement. The distal end of the fuel element unloading pipe is connected sequentially to fuel loading apparatus and a transfer apparatus. Two nozzles of the gas transport pipe are connected to set positions on the fuel element output pipe and the fuel element unloading pipe respectively. Gas driving mechanisms are connected to the gas transport pipe. An inlet of the gas driving mechanism is arranged at one end in proximity to the fuel element unloading pipe. The sealed system prevents significant oxidation of a spent fuel element due to high temperature, thus ensuring the integrity of the fuel element in the transfer apparatus, and the safety of the spent fuel unloading system can be ensured.