An apparatus for treating waste of a nuclear reactor pressure vessel includes: a suction unit inserted into the nuclear reactor pressure vessel through a plurality of through-pipes passing through a lower portion of the nuclear reactor pressure vessel to suck waste inside the nuclear reactor pressure vessel; a waste treatment part connected to the suction unit to treat the waste; and a lower collection part connected to the waste treatment part to be positioned under the nuclear reactor pressure vessel with the suction unit therebetween.

A nuclear reactor dismantlement system according to an embodiment includes bio-protective concrete including a first space into which a reactor is inserted and a second space that is connected to the first space and is expanded in the first space, a moving device that is positioned in the second space and moves the reactor, and a cutting device that is positioned in the second space and cuts the reactor.

A nuclear dismantling system for dismantling equipment contaminated with radioactive contamination, including a dismantling apparatus to be operated remotely while in a nuclear facility and a control system communicatively coupled to the dismantling apparatus to control the dismantling apparatus remotely.

A plurality of signal anomalies are identified in a number of tubes in a steam generator. Since the geometry of the steam generator is known, the location of each signal anomaly along each tube is converted into a location within the interior of the steam generator. If a plurality of signal anomalies are at locations within the steam generator that are within a predetermined proximity of one another, such a spatial confluence of signal anomalies is determined to correspond with a loose part situated within the steam generator. Additional methodologies can be employed to confirm the existence of the loose part. Historic tube sheet transition signal data can be retrieved and subtracted from present signals in order to enable the system to ignore the relatively strong eddy current sensor signal of a tube sheet which would mask the relatively weak signal from a loose part at the tube sheet transition.

A fireproof structure includes: a first heat-absorbing material that includes an inorganic porous formed body that has absorbed water, or a second heat-absorbing material that includes particles that include magnesium phosphate hydrate and a binder; and a fibrous heat-insulating material that includes inorganic fibers having a shrinkage ratio of 5% or less when allowed to stand at 1,100° C. for 24 hours.

A fireproof structure includes: a first heat-absorbing material that includes an inorganic porous formed body that has absorbed water, or a second heat-absorbing material that includes particles that include magnesium phosphate hydrate and a binder; and a fibrous heat-insulating material that includes inorganic fibers having a shrinkage ratio of 5% or less when allowed to stand at 1,100° C. for 24 hours.

Disclosed herein is a machine for cutting nozzles of reactor vessels. The machine for cutting nozzles of reactor vessels comprises a cutting unit positioned at an upper surface edge of a reactor vessel having a nozzle and having a saw blade part having different contact areas to cut the nozzle, a drive unit providing the saw blade part with rotary power, and a foreign substance suction unit provided at one end of the cutting unit in contiguity with the saw blade part to suck foreign substances generated when the nozzle is cut by the saw blade part, wherein the foreign substance suction unit sucks the foreign substances by approaching an outer peripheral surface of the nozzle when the saw blade part moves in a cutting direction of the nozzle.

There is provided a method for measuring a contact force applied to each tube constituting a tube bundle disposed in a fluid from a vibration damping member by using a probe inserted into each tube. Characteristic data defining a relationship between a value measured by the probe and the contact force is previously prepared. Then, the probe is inserted into the tube, and the contact force is calculated using the measurement value of the probe, based on the characteristic data.

There is provided a method for measuring a contact force applied to each tube constituting a tube bundle disposed in a fluid from a vibration damping member by using a probe inserted into each tube. Characteristic data defining a relationship between a value measured by the probe and the contact force is previously prepared. Then, the probe is inserted into the tube, and the contact force is calculated using the measurement value of the probe, based on the characteristic data.

A nuclear reactor is positioned on a barge which is floating in a water tank. A plurality of counter weight assemblies interconnect the barge with the tank to create a lifting force to the barge and to maintain the barge in a level position. Structure is also included for limiting horizontal movement of the counter weight of the counter weight assemblies.