KR102319702B1 - Method for Determining runoff of Radioactive Material from Steam Generator Tube Rupture in Nuclear Power Plant - Google Patents

Method for Determining runoff of Radioactive Material from Steam Generator Tube Rupture in Nuclear Power Plant Download PDF

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KR102319702B1
KR102319702B1 KR1020200131672A KR20200131672A KR102319702B1 KR 102319702 B1 KR102319702 B1 KR 102319702B1 KR 1020200131672 A KR1020200131672 A KR 1020200131672A KR 20200131672 A KR20200131672 A KR 20200131672A KR 102319702 B1 KR102319702 B1 KR 102319702B1
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steam generator
radioactive material
tube
power plant
nuclear power
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최유정
이만규
박재환
신태영
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한국수력원자력 주식회사
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    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C17/00—Monitoring; Testing ; Maintaining
    • G21C17/002—Detection of leaks
    • F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F22—STEAM GENERATION
    • F22B—METHODS OF STEAM GENERATION; STEAM BOILERS
    • F22B37/00—Component parts or details of steam boilers
    • F22B37/002—Component parts or details of steam boilers specially adapted for nuclear steam generators, e.g. maintenance, repairing or inspecting equipment not otherwise provided for
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C17/00—Monitoring; Testing ; Maintaining
    • G21C17/017—Inspection or maintenance of pipe-lines or tubes in nuclear installations
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y02E30/30—Nuclear fission reactors

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  • High Energy & Nuclear Physics (AREA)
  • Plasma & Fusion (AREA)
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Abstract

The present invention relates to a method for determining radioactive material outflow in case of a steam generator tube rupture in a nuclear power plant comprising: a step of recognizing the steam generator tube rupture; and a step of determining radioactive material outflow released outside in consideration of an full scrubbing effect in the steam generator.

Description

원자력 발전소 증기발생기 세관파단 사고시 방사성 물질 유출량 판단 방법 {Method for Determining runoff of Radioactive Material from Steam Generator Tube Rupture in Nuclear Power Plant}{Method for Determining runoff of Radioactive Material from Steam Generator Tube Rupture in Nuclear Power Plant}

본 발명은 원자력 발전소 증기발생기 세관파단 사고시 방사성 물질 유출량 판단 방법에 관한 것이다.The present invention relates to a method for determining the amount of radioactive material leakage in the event of a tube rupture accident in a steam generator in a nuclear power plant.

노심의 심각한 손상(용융)이 수반되는 원자력발전소 중대사고로 인해 증기발생기 세관파단사고(SGTR, Steam Generator Tube Rupture)가 추가로 발생하는 경우 다량의 방사성 물질이 외부로 방출될 수 있다.When a steam generator tube rupture (SGTR) additionally occurs due to a serious accident at a nuclear power plant that involves serious damage (melting) of the core, a large amount of radioactive material may be released to the outside.

실제 현장에서는 증기발생기 세관 파단부위에 물이 존재할 경우, 물에 의해 방사성 물질이 세정되는 방식인 풀스크러빙 효과에 의해 외부로 방출되는 방사성 물질은 어느정도 제거된다고 알려져 있으나, 사고 분석 시에는 풀스크러빙 현상 의한 방사성 물질 제거효과를 전혀 고려하지 않고 세관 파단부위로 방출되는 방사성 물질 전부가 그대로 외부로 방출된다는 보수적 가정에 따라 방출되는 방사성 물질을 추정하고 있다.In actual field, it is known that when water exists in the ruptured part of the tube of the steam generator, the radioactive material emitted to the outside is removed to some extent by the full scrubbing effect, which is a method in which the radioactive material is cleaned by water. The radioactive material emitted is estimated based on the conservative assumption that all the radioactive material emitted to the tubular rupture site is released to the outside without considering the radioactive material removal effect at all.

일본 등록 특허 제6466766호(2019년 01월 18일 등록)Japanese Registered Patent No. 6466766 (Registered on January 18, 2019)

삭제delete

본 발명의 목적은 원자력 발전소 증기발생기 세관파단 사고시 방사성 물질 유출량 판단 방법을 제공하는 것이다.It is an object of the present invention to provide a method for determining the amount of radioactive material leakage in the event of a tube rupture accident in a nuclear power plant steam generator.

본 발명은 원자력 발전소의 증기발생기 세관파단 사고시 방사성 물질 유출량 판단 방법에 있어서, 상기 증기발생기 세관파단 사고를 인지하는 단계, 상기 증기발생기에서의 풀스크러빙 효과를 감안하여 외부로 방출되는 방사성 물질의 유출량을 판단하는 단계를 포함하는 원자력 발전소 증기발생기 세관파단 사고시 방사성 물질 유출량 판단 방법에 관한 것이다.The present invention relates to a method for determining the amount of radioactive material outflow in case of a tube rupture accident in a steam generator of a nuclear power plant, the step of recognizing the tube breakage accident in the steam generator, and the amount of radioactive material emitted to the outside in consideration of the full scrubbing effect in the steam generator It relates to a method for determining the amount of radioactive material leakage in the event of a tube rupture accident in a nuclear power plant steam generator, comprising the step of determining.

상기 증기발생기 세관 내부에서 상기 증기발생기 2차측으로 유출되는 방사성 물질에 따른 제염계수 테이블을 마련하는 단계를 더 포함할 수 있다.The method may further include providing a decontamination coefficient table according to the radioactive material flowing out from the inside of the steam generator tube to the secondary side of the steam generator.

상기 제염계수는 상기 증기발생기 외부로 방출되는 방사성 물질의 총량 대비 세관파단시 상기 증기발생기 2차측으로 유입되는 방사성 물질 총량으로 정의된다.The decontamination factor is defined as the total amount of radioactive material introduced into the secondary side of the steam generator when the tube is broken compared to the total amount of radioactive material emitted to the outside of the steam generator.

상기 제염계수 테이블은 상기 증기발생기 세관 내부와 상기 증기발생기 2차측의 핵연료 물질 내 방사성 에어로졸 농도를 활용하여 얻어진다.The decontamination factor table is obtained by utilizing the concentration of radioactive aerosol in the nuclear fuel material inside the tube of the steam generator and on the secondary side of the steam generator.

상기 제염계수 테이블은 상기 증기발생기 2차측 수위를 활용하는 원자력 발전소 증기발생기 세관파단 사고시 방사성 물질 유출량 판단 방법이다.The decontamination coefficient table is a method of determining the amount of radioactive material outflow in the event of a tube rupture accident in a nuclear power plant steam generator using the secondary water level of the steam generator.

상기 제염계수 테이블은 상기 증기발생기 세관 내부와 상기 증기발생기 2차측의 기,액체의 온도 및 압력을 활용하여 얻어지는 원자력 발전소 증기발생기 세관파단 사고시 방사성 물질 유출량 판단 방법이다.The decontamination coefficient table is a method for determining the amount of radioactive material outflow in the event of a tube rupture accident of a nuclear power plant steam generator obtained by utilizing the temperature and pressure of the gas and liquid inside the tube of the steam generator and on the secondary side of the steam generator.

상기 제염계수 테이블은 상기 증기발생기 세관 직경을 추가로 활용하여 얻어지는 원자력 발전소 증기발생기 세관파단 사고시 방사성 물질 유출량 판단 방법이다.The decontamination coefficient table is a method for determining the amount of radioactive material outflow in the event of a tube rupture accident of a nuclear power plant steam generator obtained by additionally utilizing the tube diameter of the steam generator.

본 발명에 따르면, 원자력 발전소 증기발생기 세관파단 사고시 방사성 물질 유출량 판단 방법이 제공된다.According to the present invention, there is provided a method for determining the amount of radioactive material outflow in case of a tube rupture accident in a nuclear power plant steam generator.

도 1은 본 발명의 일실시예에 따른 원자력 발전소 증기발생기 세관파단 사고시 방사성 물질 유출량 판단 방법을 나타낸 순서도이고,
도 2은 본 발명의 일실시예에 따른 증기발생기 풀스크러빙 제염계수 테이블을 나타낸 것이다.1 is a flowchart illustrating a method for determining the amount of radioactive material leakage in the event of a tube rupture accident in a nuclear power plant steam generator according to an embodiment of the present invention;
Figure 2 shows a steam generator full scrubbing decontamination coefficient table according to an embodiment of the present invention.

이하 도면을 참조하여 본 발명을 더욱 상세히 설명한다. 첨부된 도면은 본 발명의 기술적 사상을 더욱 구체적으로 설명하기 위하여 도시한 일 예에 불과하므로 본 발명의 사상이 첨부된 도면에 한정되는 것은 아니다.Hereinafter, the present invention will be described in more detail with reference to the drawings. Since the accompanying drawings are only an example shown in order to explain the technical idea of the present invention in more detail, the spirit of the present invention is not limited to the accompanying drawings.

도 1은 본 발명의 일실시예에 따른 원자력 발전소 증기발생기 세관파단 사고시 방사성 물질 유출량 판단 방법의 순서도를 나타낸 것이다.1 is a flowchart showing a method for determining the amount of radioactive material outflow in the event of a tube rupture accident in a nuclear power plant steam generator according to an embodiment of the present invention.

본 발명의 증기발생기 세관 내부에서 먼저 증기발생기 2차측으로 유출되는 방사성 물질에 따른 제염계수 테이블을 마련한다(S100).In the steam generator tube of the present invention, first, a table of decontamination coefficients according to the radioactive material flowing out to the secondary side of the steam generator is prepared (S100).

제염계수 테이블의 x축은 증기발생기기 2차측 수위 정보를 나타내며, y축은 제염계수 값을 나타낸다. 자세한 내용은 후술한다.The x-axis of the decontamination coefficient table represents the water level information on the secondary side of the steam generator, and the y-axis represents the decontamination coefficient value. Details will be described later.

이후 원자력 발전소의 증기발생기 세관파단 사고를 인지한다(S200). Thereafter, the tube rupture accident of the steam generator of the nuclear power plant is recognized (S200).

증기발생기는 원자력 발전소 연료의 붕괴열을 냉각하는 1차측 원자로냉각재와 증기를 생산하는 2차측 급수의 경계로서, 정상운전 중 증기발생기 세관 사고가 발생할 경우 압력차로 인해 방사성 물질을 포함한 1차측 원자로냉각재가 2차측 급수로 전이된다.The steam generator is the boundary between the primary reactor coolant that cools the decay heat of fuel in a nuclear power plant and the secondary supply water that produces steam. transferred to the secondary water supply.

증기발생기 세관파단 사고는 증기발생기 누설 방사선 감시기의 경보 발생을 통해 운전원이 인지할 수 있다.The steam generator tube rupture accident can be recognized by the operator through the alarm generation of the steam generator leakage radiation monitor.

마지막으로 증기발생기에서의 풀스크러빙 효과를 감안하여 외부로 방출되는 방사성 물질의 유출량을 판단한다(S300).Finally, in consideration of the full scrubbing effect in the steam generator, the amount of outflow of the radioactive material emitted to the outside is determined (S300).

증기발생기 2차측 수위[m] 정보 확인하고 테이블에서 증기발생기 2차측 수위에 따른 제염계수 값 확인함으로써 방사성 물질의 유출량을 판단할 수 있다.By checking the water level [m] on the secondary side of the steam generator and checking the decontamination coefficient value according to the water level on the secondary side of the steam generator in the table, the amount of radioactive material outflow can be determined.

증기발생기에는 2차측 수위를 확인할 수 있는 계측기가 구비 되어 있어 2차측 수위를 실측할 수 있다.The steam generator is equipped with a measuring instrument that can check the secondary water level, so that the secondary water level can be measured.

또한, 원자력발전소 증기발생기의 설계 정보를 활용할 수 있다. In addition, design information of the steam generator of a nuclear power plant can be utilized.

다른 열수력학적 조건과 계통의 운전, 설계 조건 등이 동일하다고 할 때, 풀스크러빙 효과는 해당 수조의 수위가 증가할수록 증가한다.Assuming that other thermohydrodynamic conditions, system operation, and design conditions are the same, the full scrubbing effect increases as the water level in the corresponding tank increases.

제염계수는 증기발생기 세관파단 시 증기발생기 2차측으로 유입되는 방사성 물질 총량 대비 풀스크러빙 후 외부로 방출되는 방사성 물질 총량의 비로 정의한다.The decontamination factor is defined as the ratio of the total amount of radioactive material discharged to the outside after full scrubbing to the total amount of radioactive material flowing into the secondary side of the steam generator when the tube is broken.

[수식 1][Formula 1]

제염계수(DF, Decontamination Factor)=세관파단 시 증기발생기 2차측으로 유입되는 방사성 물질 총량/스크러빙 후 외부로 방출되는 방사성 물질 총량.Decontamination Factor (DF) = Total amount of radioactive material that flows into the secondary side of the steam generator when the tube is broken/Total amount of radioactive material that is released outside after scrubbing.

제염계수가 1인 경우 증기발생기 세관파단에 의해 세관 내부에서 증기발생기 2차측으로 유입된 방사성 물질 전부가 어떠한 방사성 물질 제거과정 없이 외부로 방출되는 것을 의미한다.When the decontamination factor is 1, it means that all the radioactive materials introduced into the secondary side of the steam generator from the inside of the customs due to the rupture of the tube of the steam generator are released to the outside without any radioactive material removal process.

제염계수 테이블의 마련을 자세히 설명하면 다음과 같다.A detailed description of the preparation of the decontamination coefficient table is as follows.

위 실시예에서는 제염계수 테이블을 먼저 마련하였지만, 본 발명은 이에 한정되지 않는다.Although the decontamination coefficient table was prepared first in the above embodiment, the present invention is not limited thereto.

제염계수 테이블은 증기발생기 세관이 파단되어 세관 내 냉각재 안에 함유되어 있던 방사성 물질이 증기발생기 2차측 물로 유입되면서 그 당시 증기 발생기 세관 내부(증기발생기 1차측)와 증기발생기 2차측의 기체 및 액체의 온도, 압력조건, 그리고 핵연료 물질 내 방사성 물질의 양을 추정하여 계산할 수 있다.The decontamination coefficient table shows the temperature of the gas and liquid inside the tube of the steam generator (primary side of the steam generator) and the secondary side of the steam generator at that time as the radioactive material contained in the coolant in the tube was broken and the water was introduced into the secondary side of the steam generator. It can be calculated by estimating the , pressure conditions, and the amount of radioactive material in the nuclear fuel material.

이 중 물에 용해되는 효과를 가진 방사성 에어로졸 물질에 대해 방사성 물질의 제거기작(impaction, sedimentation, brownian diffusion 등)에 의해 증기발생기 2차측 물 내부에서 제거되는 양을 계산할수 있다. Among these, the amount of radioactive aerosol material having the effect of dissolving in water can be calculated by the removal mechanism (impaction, sedimentation, brownian diffusion, etc.)

본 발명에서 방사성 물질이라 함은 핵연료에서 방출되는 물질 중 물에 용해되는 것으로 알려진 방사성 에어로졸을 의미하며, 제염계수 계산의 정의에서 해당 조건에서 유입되는 총량은 원자로 내에 있는 핵연료에 포함되어 있는 핵분열생성물량을 기반으로 계산할 수 있다. In the present invention, the term "radioactive material" means a radioactive aerosol known to dissolve in water among materials emitted from nuclear fuel. can be calculated based on

일반적으로 제염계수 계산을 위한 실험 측정은 주입하는 에어로졸의 농도와 계통(수조 등)을 통과 후의 에어로졸 농도를 측정하여 제염계수를 계산한다. In general, the experimental measurement for calculating the decontamination coefficient calculates the decontamination coefficient by measuring the concentration of the injected aerosol and the aerosol concentration after passing through the system (water tank, etc.).

초기 노심재고량(핵연료)에서 방사성 물질별 총량을 각 존재 분율에 따라 추정할 수 있다.In the initial core stock (nuclear fuel), the total amount of each radioactive material can be estimated according to each abundance fraction.

제염계수 계산에 반영한 증기발생기 1, 2차측 열수력 정보는 가장 보수적인 경우 다시 말하여 제염계수가 적게 나올 수 있는 경우를 가정하여 계산한다.The steam generator primary and secondary side thermal hydraulic information reflected in the calculation of the decontamination coefficient is calculated assuming that the decontamination coefficient can be small in the most conservative case.

제염계수 계산은 에어로졸 이동에 따른 풀스크러빙 영향을 계산하는 코드를 활용하여 수행할 수 있다. The decontamination coefficient calculation can be performed by using a code that calculates the full scrubbing effect according to the movement of aerosols.

제염계수 테이블 작성 시, 제염계수 계산은 풀스크러빙 효과에 직접적 영향을 미치는 국내 가압경수로형 원전의 관련 설계 및 운전 정보를 활용한다.When preparing the decontamination coefficient table, the decontamination coefficient calculation utilizes the relevant design and operation information of the domestic pressurized light water reactor type nuclear power plant that directly affects the full scrubbing effect.

제염에 영향을 미치는 주요 인자인 증기발생기 2차측 수위, 파단된 증기발생기 세관 직경, 증기발생기 1, 2차측의 기체 및 액체 온도, 압력 등의 조건에 원전 고유정보를 반영할 수 있다.The nuclear power plant-specific information can be reflected in conditions such as the water level on the secondary side of the steam generator, the diameter of the broken steam generator tube, and the gas and liquid temperatures and pressures on the primary and secondary sides of the steam generator, which are major factors affecting decontamination.

테이블에서 얻은 결과 근거로 증기발생기 세관파단 사고 시 증기발생기 내에서 발생하는 풀스크러빙현상에 의한 방사성 물질 제염효과 여부 판단할 수 있다.Based on the results obtained from the table, it can be judged whether the radioactive material decontamination effect due to the full scrubbing phenomenon that occurs in the steam generator in the event of a tube rupture accident in the steam generator.

도출된 제염계수를 활용하여, 사고로 인해 외부로 방출되는 방사성 물질에 의한 선량 평가를 계산할 수 있다.By using the decontamination factor derived, it is possible to calculate the dose evaluation by radioactive materials emitted to the outside due to an accident.

증기발생기 2차측 수위가 테이블에 제시된 증기발생기 수위 값 사이의 값인 경우에는 내삽법을 이용하여 원하는 값을 구한다.If the water level on the secondary side of the steam generator is between the level values of the steam generator shown in the table, the desired value is obtained using the interpolation method.

풀스크러빙 효과에 의한 방사성 물질의 제거로 인해 외부로 방출되는 실제 방사성 물질량 평가의 보수성 완화 및 실제적인 값의 제공이 가능하며, 이로 인한 증기발생기 세관판단 시 외부로의 방사성 물질 방출에 따른 방사선량 값의 보수성이 저감된다.Due to the removal of radioactive material by the full scrubbing effect, it is possible to alleviate the conservativeness of the evaluation of the actual amount of radioactive material emitted to the outside and provide a practical value. is reduced.

이상으로 본 발명 내용의 특정한 부분을 상세히 기술하였는바, 당업계의 통상의 지식을 가진 자에게 있어서, 이러한 구체적 기술은 단지 바람직한 실시 양태일 뿐이며, 이에 의해 본 발명의 범위가 제한되는 것이 아닌 점은 명백할 것이다. 따라서, 본 발명의 실질적인 범위는 첨부된 청구항들과 그것들의 등가물에 의하여 정의된다고 할 것이다. As described above in detail a specific part of the present invention, for those of ordinary skill in the art, it is clear that this specific description is only a preferred embodiment, and the scope of the present invention is not limited thereby. something to do. Accordingly, it is intended that the substantial scope of the present invention be defined by the appended claims and their equivalents.

삭제delete

Claims (7)

원자력 발전소의 증기발생기 세관파단 사고시 방사성 물질 유출량 판단 방법에 있어서,
상기 증기발생기 세관파단 사고를 인지하는 단계;
상기 증기발생기에서의 풀스크러빙 효과를 감안하여 외부로 방출되는 방사성 물질의 유출량을 판단하는 단계를 포함하며,
상기 증기발생기 세관 내부에서 상기 증기발생기 2차측으로 유출되는 방사성 물질에 따른 제염계수 테이블을 마련하는 단계를 더 포함하는 방법.In the method for determining the amount of radioactive material leakage in the case of a tube rupture accident of a steam generator of a nuclear power plant,
Recognizing the steam generator tube rupture accident;
Comprising the step of determining the amount of outflow of radioactive material emitted to the outside in consideration of the full scrubbing effect in the steam generator,
The method further comprising the step of providing a decontamination coefficient table according to the radioactive material flowing out from the inside of the steam generator tube to the secondary side of the steam generator. 삭제delete 제1항에 있어서,
상기 제염계수는
상기 증기발생기 외부로 방출되는 방사성 물질의 총량 대비 세관파단시 상기 증기발생기 2차측으로 유입되는 방사성 물질 총량으로 정의되는 방법.According to claim 1,
The decontamination coefficient is
A method defined as the total amount of radioactive material flowing into the secondary side of the steam generator when the tube is ruptured compared to the total amount of radioactive material emitted to the outside of the steam generator. 제1항에 있어서,
상기 제염계수 테이블은 상기 증기발생기 세관 내부와 상기 증기발생기 2차측의 핵연료 물질 내 방사성 에어로졸 농도를 활용하여 얻어지는 방법.According to claim 1,
The decontamination coefficient table is obtained by utilizing the concentration of radioactive aerosol in the nuclear fuel material inside the tube of the steam generator and on the secondary side of the steam generator. 제1항에 있어서,
상기 제염계수 테이블은 상기 증기발생기 2차측 수위를 활용하는 원자력 발전소 증기발생기 세관파단 사고시 방사성 물질 유출량 판단 방법.According to claim 1,
The decontamination coefficient table is a method of determining the amount of radioactive material outflow in the event of a tube rupture accident in a nuclear power plant steam generator using the secondary water level of the steam generator. 제1항에 있어서,
상기 제염계수 테이블은 상기 증기발생기 세관 내부와 상기 증기발생기 2차측의 기,액체의 온도 및 압력을 활용하여 얻어지는 원자력 발전소 증기발생기 세관파단 사고시 방사성 물질 유출량 판단 방법.According to claim 1,
The decontamination coefficient table is a method for determining the amount of radioactive material outflow at the time of a tube rupture accident of a nuclear power plant steam generator obtained by using the temperature and pressure of the gas and liquid inside the tube of the steam generator and the secondary side of the steam generator. 제1항에 있어서,
상기 제염계수 테이블은 상기 증기발생기 세관 직경을 추가로 활용하여 얻어지는 원자력 발전소 증기발생기 세관파단 사고시 방사성 물질 유출량 판단 방법.According to claim 1,
The decontamination coefficient table is a method of determining the amount of radioactive material outflow in case of a nuclear power plant steam generator tube rupture accident obtained by additionally utilizing the tube diameter of the steam generator.
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Citations (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP5235139B2 (en) * 2006-03-07 2013-07-10 アレヴァ ゲゼルシャフト ミット ベシュレンクテル ハフツング Nuclear equipment and closure device in its containment vessel
JP2015075441A (en) * 2013-10-11 2015-04-20 日立Ｇｅニュークリア・エナジー株式会社 Nuclear reactor equipment unloading or fuel debris unloading method and apparatus therefor
KR20200053393A (en) * 2018-11-08 2020-05-18 한국과학기술원 System and method for mitigating dispersion of radioactive substance in steam generator tube rupture accidents

Patent Citations (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP5235139B2 (en) * 2006-03-07 2013-07-10 アレヴァ ゲゼルシャフト ミット ベシュレンクテル ハフツング Nuclear equipment and closure device in its containment vessel
JP2015075441A (en) * 2013-10-11 2015-04-20 日立Ｇｅニュークリア・エナジー株式会社 Nuclear reactor equipment unloading or fuel debris unloading method and apparatus therefor
KR20200053393A (en) * 2018-11-08 2020-05-18 한국과학기술원 System and method for mitigating dispersion of radioactive substance in steam generator tube rupture accidents

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