An optical fiber penetration is disposed in a sleeve provided through a partition wall that separates a first space and a second space. The optical fiber penetration includes a first optical fiber cable and a second optical fiber cable each having a thin tube formed of metal and an optical fiber strand inserted in the thin tube, a cylindrical body that is formed of metal and is disposed in an axial direction of the sleeve, an interior of which includes the first optical fiber cable on a side of the first space and the second optical fiber cable on a side of the second space, an internal connector configured to connect the first optical fiber cable with the second optical fiber cable in the interior of the cylindrical body, and a first lid and a second lid configured to close one end and the other end of the cylindrical body.

Provided is a remotely operated manipulator which can be applied to a space which is wider on a back side than at an opening part, which has a simple structure, high stiffness, and high reliability. The remotely operated manipulator of the present invention includes: a circular base fixed to a wall surface; a beam which rotates on the circular base; a trolley which moves on the beam; and a mast which is raised and lowered with respect to the trolley and is mounted with a tool unit at a tip. Stiffness is improved by directly fixing the beam to the wall surface by a beam fixing device. Further, a work region is expanded by mounting a bending mast on the tip of the mast.

A device for removing shielding balls from calandria of a heavy water reactor is provided. The device includes a head for moving the shielding balls positioned inside of an end shield of the calandria to an outside of the end shield; and a mover for moving the head to the end shield of the calandria. The head includes a head body, an opening former installed on the head body and configured to form an opening in the end shield, and a gate installed on the head body and configured to control an amount of the shielding balls discharged to the outside through the opening.

An in-vessel cooling and power generation system according to the present disclosure may include a small scale reactor vessel, a heat exchange section provided inside the reactor vessel, and formed to supply supercritical fluid to receive heat from a reactor coolant system in the reactor vessel, an electric power production section comprising a supercritical turbine formed to produce electric energy using the energy of the supercritical fluid whose temperature has increased while receiving heat from the reactor coolant system, a cooling section configured to exchange heat with the supercritical fluid discharged after driving the supercritical turbine to shrink a volume of the supercritical fluid, wherein the supercritical fluid that has received heat from the reactor coolant system in the heat exchange section is formed to circulate through the electric power production section, and the cooling section.

An in-vessel cooling and power generation system according to the present disclosure may include a small scale reactor vessel, a heat exchange section provided inside the reactor vessel, and formed to supply supercritical fluid to receive heat from a reactor coolant system in the reactor vessel, an electric power production section comprising a supercritical turbine formed to produce electric energy using the energy of the supercritical fluid whose temperature has increased while receiving heat from the reactor coolant system, a cooling section configured to exchange heat with the supercritical fluid discharged after driving the supercritical turbine to shrink a volume of the supercritical fluid, wherein the supercritical fluid that has received heat from the reactor coolant system in the heat exchange section is formed to circulate through the electric power production section, and the cooling section.

The present invention provides a corrosion-resistant structure for a high-temperature water system comprising: a structural material 1; and a corrosion-resistant film 3 formed from a substance containing at least one of La and Y deposited on a surface in a side that comes in contact with a cooling water 4, of the structural material 1 which constitutes the high-temperature water system that passes a cooling water 4 of high temperature therein. Due to above construction, there can be provided the corrosion-resistant structure and a corrosion-preventing method capable of operating a plant without conducting a water chemistry control of cooling water by injecting chemicals.

A pressurized water reactor (PWR) includes a cylindrical pressure vessel defining a sealed volume, a nuclear reactor core disposed in a lower portion of the cylindrical pressure vessel, one or more control rod drive mechanisms (CRDMs) disposed in the cylindrical pressure vessel above the nuclear reactor core, and an annular steam generator surrounding the nuclear reactor core and the CRDM. In some such PWR, a cylindrical riser is disposed coaxially inside the pressure vessel and inside the annular steam generator and surrounds the nuclear reactor core and the CRDM, and the steam generator is disposed coaxially inside the cylindrical pressure vessel in an annular volume defined by the cylindrical pressure vessel and the cylindrical riser. In other such PWR, the steam generator is disposed coaxially outside of and secured with the cylindrical pressure vessel.

Disclosed is a method for building a nuclear reactor installation including a containment chamber surrounded by a protective casing. The method is characterised by the following essential construction phases: finding or preparing a cavern (2) in rocky ground or a mountain (3) which is connected to the outside world via a tunnel or shaft (4), constructing or introducing a sealed protective casing (5) made of steel which delimits the containment chamber (1) forming an enveloping intermediate chamber volume (6) between the protective casing (5) and the cavern walls (2′), and, filling the intermediate chamber (6) with concrete or cement (6′), with the exception of the tunnel or shaft (4).

Disclosed is a method for building a nuclear reactor installation including a containment chamber surrounded by a protective casing. The method is characterised by the following essential construction phases: finding or preparing a cavern (2) in rocky ground or a mountain (3) which is connected to the outside world via a tunnel or shaft (4), constructing or introducing a sealed protective casing (5) made of steel which delimits the containment chamber (1) forming an enveloping intermediate chamber volume (6) between the protective casing (5) and the cavern walls (2′), and, filling the intermediate chamber (6) with concrete or cement (6′), with the exception of the tunnel or shaft (4).

A system for servicing a nuclear reactor module comprises a crane operable to attach to the nuclear reactor module, wherein the crane includes provisions for routing signals from one or more sensors of the nuclear reactor module to one or more sensor receivers.