JP2016024154A5 - - Google Patents
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- JP2016024154A5 JP2016024154A5 JP2014150569A JP2014150569A JP2016024154A5 JP 2016024154 A5 JP2016024154 A5 JP 2016024154A5 JP 2014150569 A JP2014150569 A JP 2014150569A JP 2014150569 A JP2014150569 A JP 2014150569A JP 2016024154 A5 JP2016024154 A5 JP 2016024154A5
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- neutron
- fuel debris
- state estimation
- subcritical state
- multiplication factor
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- 239000000446 fuel Substances 0.000 claims 31
- 238000004088 simulation Methods 0.000 claims 14
- 230000004907 flux Effects 0.000 claims 5
- 239000000203 mixture Substances 0.000 claims 5
- 239000000284 extract Substances 0.000 claims 3
- 239000000463 material Substances 0.000 claims 2
- 238000005259 measurement Methods 0.000 claims 2
- 239000003758 nuclear fuel Substances 0.000 claims 2
- 238000002360 preparation method Methods 0.000 claims 1
Claims (10)
前記燃料デブリより発せられる中性子を測定する中性子検出器と、
前記取得された画像データ及び３次元形状データに基づき前記燃料デブリの状態をシミュレーションし、シミュレーション結果及び計測された中性子に基づき前記燃料デブリの中性子増倍率を抽出し、前記燃料デブリの未臨界度を推定する未臨界状態推定装置と、を備えることを特徴とする未臨界状態推定システム。 Acquiring an image of fuel debris, an image acquisition unit for generating a three-dimensional shape data based on the acquisition image,
A neutron detector for measuring neutrons emitted from the fuel debris;
Simulating the state of the fuel debris on the basis of the image data and the three-dimensional shape data the obtained extracts neutron multiplication factor of the fuel debris based on neutron simulation results and measured, subcritical of the fuel debris A subcritical state estimation system comprising: a subcritical state estimation device that estimates a degree.
前記未臨界状態推定装置は、
前記画像データ及び３次元形状データにおける燃料デブリの境界を設定する入力条件作成部と、
少なくとも、前記燃料デブリに関する核燃料物質の組成及び原子炉建屋内の構造物の組成を格納する構造物データベースと、
前記設定された燃料デブリの境界及び前記構造物データベースに格納される組成に基づき前記燃料デブリの中性子増倍率を抽出するシミュレーション部と、
前記シミュレーション結果及び前記中性子検出器により測定された中性子に基づき、前記燃料デブリの未臨界度を推定する未臨界推定部と、を有することを特徴とする未臨界状態推定システム。 The subcritical state estimation system according to claim 1,
The subcritical state estimation device is:
An input condition creation unit for setting a boundary of fuel debris in the image data and the three-dimensional shape data;
A structure database storing at least the composition of nuclear fuel material and the composition of the structure in the reactor building related to the fuel debris;
A simulation unit for extracting a neutron multiplication factor of the fuel debris based on the set boundary of the fuel debris and the composition stored in the structure database;
A subcritical state estimation system, comprising: a subcriticality estimation unit that estimates the subcriticality of the fuel debris based on the simulation result and the neutrons measured by the neutron detector.
前記シミュレーション部は、シミュレーションモデル上での中性子検出器により得られる燃料デブリの中性子フラックスと中性子増倍率との関係を前記シミュレーション結果として出力し、
前記未臨界推定部は、前記中性子検出器により測定された中性子フラックスと、前記中性子フラックスと中性子増倍率との関係から、前記燃料デブリの中性子増倍率を抽出し、前記未臨界度として出力することを特徴とする未臨界状態推定システム。 The subcritical state estimation system according to claim 2,
The simulation unit outputs, as the simulation result, a relationship between a neutron flux and a neutron multiplication factor of fuel debris obtained by a neutron detector on a simulation model,
The subcritical estimation unit extracts the neutron multiplication factor of the fuel debris from the relationship between the neutron flux measured by the neutron detector and the neutron flux and the neutron multiplication factor, and outputs the neutron multiplication factor as the subcriticality. Subcritical state estimation system characterized by
前記画像取得部が先端部に取り付けられた第１の支持部材と、
前記中性子検出器が先端部に取り付けられた第２の支持部材と、
前記１及び第２の支持部材を原子炉圧力容器内で鉛直方向に上下動可能とし、前記未臨界状態推定装置と電気的に接続される移動装置を備えることを特徴とする未臨界状態推定システム。 In the subcritical state estimation system according to any one of claims 1 to 3,
A first support member having the image acquisition unit attached to the tip;
A second support member having the neutron detector attached to the tip;
A subcritical state estimation system comprising a moving device that allows the first and second support members to move vertically in a reactor pressure vessel and is electrically connected to the subcritical state estimation device. .
前記燃料デブリが原子炉建屋内の構造物に侵食する状態において、前記シミュレーション部は、前記画像取得部からの構造物上の燃料デブリの３次元形状データにより得られる前記構造物上の燃料デブリの体積を用いて前記中性子増倍率を算出することを特徴とする未臨界状態推定システム。 In the subcritical state estimation system according to any one of claims 2 to 4,
In the state that erodes structure of the fuel debris Hara child reactor building, the simulation unit, the fuel debris on the structure obtained by the three-dimensional shape data of fuel debris on structure creation from the image acquisition unit A subcritical state estimation system, wherein the neutron multiplication factor is calculated using the volume of the neutron.
前記燃料デブリが原子炉建屋内の構造物に侵食する状態において、
前記シミュレーション部は、シミュレーションモデル上の前記構造物に侵食する燃料デブリに対し、複数の中性子検出器の配置位置を設定し、当該設定された配置位置毎に、前記燃料デブリの中性子フラックスと中性子増倍率との関係を求め、当該求めた中性子フラックスと中性子増倍率の関係の変化が最小となる中性子検出器の配置位置を求めることを特徴とする未臨界状態推定システム。 In the subcritical state estimation system according to any one of claims 2 to 4,
In the state that erodes structure of the fuel debris Hara child reactor building,
The simulation unit sets an arrangement position of a plurality of neutron detectors for fuel debris that erodes the structure on the simulation model, and the neutron flux and neutron increase of the fuel debris are set for each of the set arrangement positions. A subcritical state estimation system characterized by obtaining a relationship with magnification and obtaining an arrangement position of a neutron detector that minimizes a change in the relationship between the obtained neutron flux and neutron multiplication factor.
前記シミュレーション部は、シミュレーションモデル上での中性子検出器により得られる燃料デブリの中性子計数率と中性子増倍率との関係を前記シミュレーション結果として出力し、
前記未臨界推定部は、前記中性子検出器により測定された中性子計数率と、前記中性子計数率と中性子増倍率との関係から、前記燃料デブリの中性子増倍率を抽出し、前記未臨界度として出力することを特徴とする未臨界状態推定システム。 The subcritical state estimation system according to claim 2,
The simulation unit outputs, as the simulation result, a relationship between a neutron count rate and a neutron multiplication factor of fuel debris obtained by a neutron detector on a simulation model,
The subcritical estimator extracts the neutron multiplication factor of the fuel debris from the neutron count rate measured by the neutron detector and the relationship between the neutron count rate and the neutron multiplication factor, and outputs it as the subcriticality A subcritical state estimation system characterized by:
先端部に画像取得部が設置される第１の支持部材を、前記原子炉建屋内で鉛直方向に下降させ、前記画像取得部を前記燃料デブリの近傍に位置付ける工程と、
先端部に中性子検出器が設置される第２の支持部材を、前記原子炉建屋内で鉛直方向に下降させ、前記中性子検出器を前記燃料デブリの近傍に位置付ける工程と、
前記画像取得部により取得された前記燃料デブリの画像データ及び３次元形状データに基づき前記燃料デブリの状態をシミュレーションする工程と、
シミュレーション結果及び前記中性子検出器による計測結果に基づき前記燃料デブリの中性子増倍率を抽出し、前記燃料デブリの未臨界度を推定する未臨界度推定工程からなることを特徴とする未臨界状態推定方法。 A subcritical state estimation method for estimating the subcriticality of fuel debris existing in a reactor building,
A step of lowering a first support member having an image acquisition unit installed at a distal end thereof in a vertical direction in the reactor building, and positioning the image acquisition unit in the vicinity of the fuel debris;
A step of vertically moving a second support member having a neutron detector installed at a tip thereof in the reactor building, and positioning the neutron detector in the vicinity of the fuel debris;
Simulating the state of the fuel debris based on the image data and three-dimensional shape data of the fuel debris acquired by the image acquisition unit;
Simulation results and extracting neutron multiplication factor of the fuel debris based on the measurement result of the neutron detector, subcritical state, comprising the subcriticality estimating step of estimating the subcriticality of the fuel debris Estimation method.
前記シミュレーションする工程は、前記画像データ及び３次元形状データにおける燃料デブリの境界を設定する工程を含み、
前記未臨界度推定工程は、少なくとも前記燃料デブリに関する核燃料物質の組成及び原子炉建屋内の構造物の組成を格納する構造物データベースを参照し、前記シミュレーション結果と前記中性子検出器による計測結果に基づき前記燃料デブリの中性子増倍率を抽出する工程を含むことを特徴とする未臨界状態推定方法。 In the subcritical state estimation method according to claim 8,
It said step of simulating includes the step of setting the boundaries of fuel debris in the image data and the three-dimensional shape data,
The subcriticality estimation step refers to a structure database storing at least the composition of nuclear fuel material and the composition of the structure in the reactor building related to the fuel debris, and based on the simulation result and the measurement result by the neutron detector A subcritical state estimation method comprising a step of extracting a neutron multiplication factor of the fuel debris.
前記画像取得部及び前記中性子検出器を前記燃料デブリの近傍に位置付ける工程の前に、前記原子炉建屋内の原子炉圧力容器の上方に作業台を設置し、前記第１及び第２の支持部材を上下動させると共に、作業台上を水平方向に移動可能な移動装置を、前記作業台に設置する準備工程を有することを特徴とする未臨界状態推定方法。 In the subcritical state estimation method according to claim 9,
Before the step of positioning the image acquisition unit and the neutron detector in the vicinity of the fuel debris, a work table is installed above a reactor pressure vessel in the reactor building, and the first and second support members with vertically moving, and the moving device movable on work platform horizontally, subcritical state estimation method characterized by having a preparation step of installing the work surface.
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| JP6472402B2 (en) * | 2016-03-08 | 2019-02-20 | 株式会社日立パワーソリューションズ | Radioactive waste management system and radiological waste management method |
| JP6814049B2 (en) * | 2017-01-13 | 2021-01-13 | 原子燃料工業株式会社 | Subcriticality measurement method for nuclear fuel |
| JP6871148B2 (en) * | 2017-12-15 | 2021-05-12 | 株式会社東芝 | In-core condition measuring device and in-core condition measuring method |
| CN110175744A (en) * | 2019-04-23 | 2019-08-27 | 中国核电工程有限公司 | A kind of data processing method of nuclear power plant's accident treatment directive/guide confirmation |
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| JP3041101B2 (en) * | 1991-09-27 | 2000-05-15 | 株式会社東芝 | Measurement method of effective multiplication factor of spent fuel assembly loading system |
| JPH0659085A (en) * | 1992-08-12 | 1994-03-04 | Mitsui Eng & Shipbuild Co Ltd | Non-criticality measuring system for spent fuel assembly and non-criticality measurement |
| JP2001281384A (en) * | 2000-03-28 | 2001-10-10 | Toshiba Corp | Monitoring method of critical approach and measuring jig for monitoring |
| JP4649122B2 (en) * | 2004-05-31 | 2011-03-09 | 株式会社東芝 | Critical safety design method for spent fuel transportation and storage equipment |
| JP5761063B2 (en) * | 2012-02-09 | 2015-08-12 | 東京電力株式会社 | Debris location method |
| JP6099876B2 (en) * | 2012-03-29 | 2017-03-22 | 三菱重工業株式会社 | Core analysis program and analysis device |
| JP5844702B2 (en) * | 2012-08-29 | 2016-01-20 | 日立Ｇｅニュークリア・エナジー株式会社 | Fuel debris recovery method and apparatus |
| US9423516B2 (en) * | 2013-03-15 | 2016-08-23 | Westinghouse Electric Company Llc | Systems and methods for spent fuel pool subcriticality measurement and monitoring |
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