Korea Hydro & Nuclear Power Patente

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A method for sampling and characterizing a large concrete container wall block according to an embodiment of another aspect of the present disclosure includes cutting at least a portion of a large concrete container to form a concrete container wall block, placing the concrete container wall block inside a sampling and characterization space provision device, detaching the detachable surface dose rate measuring device and the detachable sampling device disposed in the sampling and characterization space provision device and moving the detachable surface dose rate measuring device and the detachable sampling device so as to have a predetermined distance from the concrete container wall block, placing the detachable surface dose rate measuring device and the detachable sampling device so that the detachable surface dose rate measuring device and the detachable sampling device do not interfere with each other with respect to the concrete container wall block, and placing a plurality of the detachable surface dose rate measuring devices and the detachable sampling devices in a spaced-apart manner.

A concrete overpacking structure for a high-integrity container is disclosed. The concrete overpacking structure for the high-integrity container as a concrete structure for overpacking while loading and storing high-integrity containers (HICs) containing radioactive waste, includes a structure body having a concrete container part and a concrete cover part for overpacking the high-integrity container; and a sampling port part formed on a side of the structure body while forming a sample for collection for evaluating the resistance characteristics of the structure body.

A system for cutting and dismantling a large concrete container and evaluating disposal suitability according to an embodiment of the present invention includes a vertical and horizontal cutting apparatus for large concrete containers and solidified forms, capable of vertically and horizontally cut concrete containers and solidified forms, a cut block separating apparatus for separating a solidified form block, a grouting concrete block, an external container block from the cut blocks of the containers and the solidified forms cut by the vertical and horizontal cutting apparatus for containers and solidified forms, and a compliant disposal apparatus configured to determine clearance or disposal suitability with respect to the solidified form block, the grouting concrete block, and the external container block individually separated by the cut block separating apparatus, respectively, and execute clearance or disposal when clearance or disposal suitability requirements are satisfied.

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The present invention relates to a method for producing a nuclear design core model accounting for load following, the method comprising the steps of: receiving load-following requirements for a corresponding cycle, wherein the load-following requirements include the amount of power reduction, the number of load-following operations, and at least one of the time or duration of operation at reduced power; determining the amount of insertion of a control rod on the basis of the load-following requirements; determining the duration of insertion of the control rod on the basis of the amount of insertion of the control rod and the maximum insertion limit thereof; determining the time of insertion of the control rod by simulating core combustion by reflecting the duration of insertion of the control rod in a nuclear design code at each of a plurality of time points of the corresponding cycle; and producing a nuclear design core model accounting for load following on the basis of the determined amount of insertion of the control rod, the determined duration of insertion of the control rod, and the determined time of insertion of the control rod.

A rail-type large concrete drum cutting and dismantling system includes: a moving rail that loads a large concrete drum that is a radioactive waste to linearly move the large concrete drum to a predetermined position; a rotating platform that sequentially rotates the large concrete drum disposed at the predetermined position to be moved along the moving rail at a predetermined angle according to a predetermined cutting and dismantling control program; a guide rail device that is installed at a predetermined distance around the rotating platform, disposes a cutting device at a predetermined height with respect to the rotating platform, and moves the cutting device at a predetermined angle at the predetermined height; a cutting and dismantling device that cuts and dismantles the large concrete drum while moving along the guide rail device at a predetermined angle; and a control device that remotely controls the moving rail, the rotating platform, the guide rail device, and the cutting and dismantling device according to the cutting and dismantling control program.

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The present invention relates to a method for cutting a nuclear reactor and inserting cut materials, the method comprising the steps of: preparing cut materials by cutting a nuclear reactor through a plurality of processes; classifying the cut materials into a plurality of stack shapes; and inserting the cut materials into a packaging container according to the stack shapes, wherein the packaging container includes an external container, an internal container and a cover, and the inserting step includes the steps of: preparing the external container; accommodating the internal container in the external container; and mounting the cover on the upper portion of the internal container.

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The present invention relates to a method for controlling a part strength control element assembly to enable turbine load-following, comprising the steps of: identifying operation driving characteristics of a part strength control element assembly according to turbine loads through simulation of power plant-simulation calculations with varying turbine load; determining a maximum insertion position within the core of the part strength control element assembly on the basis of the operation driving characteristics; deriving a target position of the part strength control element assembly according to turbine load on the basis of the maximum insertion position; and controlling the insertion position of the part strength control element assembly according to the target position.

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The present invention relates to a dry storage module for the spent nuclear fuel of a vertical light water reactor, and to a dry storage module with an improved air outlet and cylinder body mounting method, and a system comprising same, the module comprising: a case for forming a hexahedral accommodation space; a plurality of storage parts, which are arranged in two rows in the accommodation space, store the spent nuclear fuel and are elongated; a hexahedral module part for accommodating the storage parts; canisters in which the spent nuclear fuel is loaded; cylinder bodies each encompassing the canister; cylinder supports for attaching/detaching the cylinder body to/from the module part; an air inlet positioned at a side of the upper portion of the case; an air outlet positioned in the lower portion of the case; and shielding grids disposed in each of the inlet and the outlet.

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