JP6132782B2 - Method for recovering molten nuclear fuel material - Google Patents

Method for recovering molten nuclear fuel material Download PDF

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JP6132782B2
JP6132782B2 JP2014029583A JP2014029583A JP6132782B2 JP 6132782 B2 JP6132782 B2 JP 6132782B2 JP 2014029583 A JP2014029583 A JP 2014029583A JP 2014029583 A JP2014029583 A JP 2014029583A JP 6132782 B2 JP6132782 B2 JP 6132782B2
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fuel material
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molten nuclear
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JP2015152564A (en
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川野　昌平
昌平 川野
雅貴 田村
雅貴 田村
福田　健
健 福田
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Toshiba Corp
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Description

本発明は原子力発電プラントの事故時に溶融した核燃料物質の回収方法に関する。   The present invention relates to a method for recovering nuclear fuel material melted at the time of an accident in a nuclear power plant.

原子力発電プラントは、蒸気発生器、高圧タービン、低圧タービン、復水器、給水ポンプ、給水加熱器を順次経て、再び原子炉へ戻る循環サイクルで構成されており、蒸気発生器で発生した蒸気によって高圧タービンおよび低圧タービンを駆動して発電機を作動させ、発電を行っている。原子力発電プラントのうち沸騰水型原子力発電プラント（ＢＷＲ）では原子炉で循環水を沸騰させており、原子炉が蒸気発生器を兼ねている。   A nuclear power plant consists of a circulation cycle that goes back to the reactor again through the steam generator, high-pressure turbine, low-pressure turbine, condenser, feed water pump, feed water heater, and the steam generated by the steam generator. The generator is operated by driving the high-pressure turbine and the low-pressure turbine to generate electricity. Among nuclear power plants, boiling water nuclear power plants (BWR) boil circulating water in a nuclear reactor, and the nuclear reactor also serves as a steam generator.

一方、大災害等により原子力発電プラントに供給する電源が失われると、原子炉への給水が停止し、原子炉に装荷した核燃料物質が溶融する可能性がある。こうした過酷事故が生じた場合、原子炉を冷温停止させた後、溶融核燃料物質を炉心から安全に取り出す必要がある。   On the other hand, if the power supplied to the nuclear power plant is lost due to a major disaster or the like, the water supply to the nuclear reactor may stop and the nuclear fuel material loaded in the nuclear reactor may melt. When such a severe accident occurs, it is necessary to safely remove the molten nuclear fuel material from the reactor core after the reactor is cold stopped.

このような溶融核燃料物質の回収手段として、原子炉や格納容器の下部に堆積した溶融核燃料物質を切削具により切削し、搬送装置により炉外へ搬出する手段が提案されている（特許文献１）。   As a means for recovering such molten nuclear fuel material, a means has been proposed in which molten nuclear fuel material deposited in the lower part of a nuclear reactor or a containment vessel is cut by a cutting tool and carried out of the reactor by a transfer device (Patent Document 1). .

特開２０１３−１９８７５号公報JP 2013-19875 A

溶融核燃料物質にはウラン２３５が含まれているため、回収作業中に不用意に取り扱えば、希に核***の連鎖反応が起こり、再臨界に達する可能性がある。例えば、回収した溶融核燃料物質を収納容器に収納する場合、収納容器の内容積によっては収納された溶融核燃料物質により再臨界が起きる可能性がある。このため、収納容器の内容積を制限する等、溶融核燃料物質について厳格な再臨界管理が必要となっている。   Since the molten nuclear fuel material contains uranium 235, if it is handled carelessly during the recovery operation, there is a possibility that a fission chain reaction rarely occurs and the criticality is reached. For example, when the recovered molten nuclear fuel material is stored in a storage container, recriticality may occur due to the stored molten nuclear fuel material depending on the internal volume of the storage container. For this reason, strict recriticality management is required for the molten nuclear fuel material, such as limiting the internal volume of the storage container.

一方、溶融核燃料物質の一部は、炉心シュラウド、炉心支持板、制御棒案内管等の金属製の原子炉構造物に付着して存在している。その際、溶融核燃料物質を原子炉構造物とともに収納容器に回収した場合、再臨界管理が必要な溶融核燃料物質と再臨界管理の必要がない原子炉構造物が収納容器内に混在することになり、溶融核燃料物質に対して厳格で精度の高い再臨界管理を行うことができないという課題がある。   On the other hand, a part of the molten nuclear fuel material is attached to a metal reactor structure such as a core shroud, a core support plate, and a control rod guide tube. At that time, if the molten nuclear fuel material is recovered together with the reactor structure in the containment vessel, the molten nuclear fuel material that requires recriticality management and the nuclear reactor structure that does not require recriticality management will coexist in the containment vessel. However, there is a problem that strict and highly accurate recriticality control cannot be performed on the molten nuclear fuel material.

本発明は上記課題を解決するためになされたものであり、溶融核燃料物質と原子炉構造物を分別して回収することで、溶融核燃料物質に対し厳格で精度の高い再臨界管理を行うことができる溶融核燃料物質の回収方法を提供することを目的とする。   The present invention has been made to solve the above-mentioned problems, and by separating and recovering the molten nuclear fuel material and the reactor structure, it is possible to perform strict and highly accurate recriticality management for the molten nuclear fuel material. An object is to provide a method for recovering molten nuclear fuel material.

上記課題を解決するために、本発明に係る溶融核燃料物質の回収方法は、溶融核燃料物質が付着した原子炉構造物から前記溶融核燃料物質と前記原子炉構造物を分別回収する溶融核燃料物質の回収方法において、回収対象物の電気電導度を測定する工程と、前記回収対象物の電気電導度が基準値以下の場合に当該回収対象物が溶融核燃料物質と判定し、電気電導度が基準値以上の場合に原子炉構造物と判定する判定工程と、回収対象物が溶融核燃料物質と判定された場合に当該溶融核燃料物質に衝撃荷重を加え破砕する破砕工程と、前記破砕された溶融核燃料物質を回収する回収工程と、を有することを特徴とする。 In order to solve the above-mentioned problem, a method for recovering a molten nuclear fuel material according to the present invention is a recovery of a molten nuclear fuel material that separates and recovers the molten nuclear fuel material and the reactor structure from a nuclear reactor structure to which the molten nuclear fuel material is adhered. In the method, the step of measuring the electrical conductivity of the recovery object, and when the electrical conductivity of the recovery object is less than a reference value, the recovery object is determined to be a molten nuclear fuel material, and the electrical conductivity is greater than the reference value A determination step for determining a nuclear reactor structure, a crushing step for crushing the molten nuclear fuel material by applying an impact load when the recovery target is determined to be a molten nuclear fuel material, and the crushed molten nuclear fuel material A recovery step of recovering.

本発明によれば、再臨界管理が必要な溶融核燃料物質と再臨界管理の必要がない原子炉構造物を分別して回収することにより、溶融核燃料物質に対して厳格で精度の高い再臨界管理を行うことができる。   According to the present invention, rigorous and highly accurate recriticality management is performed on molten nuclear fuel material by separating and recovering the nuclear fuel material that requires recriticality management and the reactor structure that does not require recriticality management. It can be carried out.

本実施形態に係る原子力プラントの構成図。The block diagram of the nuclear power plant which concerns on this embodiment. （ａ）〜（ｃ）は第１の実施形態に係る溶融核燃料物質の回収作業例を示す図。(A)-(c) is a figure which shows the collection | recovery operation example of the molten nuclear fuel material which concerns on 1st Embodiment. （ａ）〜（ｃ）は第１の実施形態に係る原子炉構造物の回収作業例を示す図。(A)-(c) is a figure which shows the collection | recovery operation example of the nuclear reactor structure which concerns on 1st Embodiment. （ａ）〜（ｃ）は第２の実施形態に係る溶融核燃料物質の回収作業例を示す図。(A)-(c) is a figure which shows the collection | recovery operation example of the molten nuclear fuel material which concerns on 2nd Embodiment.

以下、本発明に係る溶融核燃料物質の回収方法の実施形態について、図面を参照して説明する。
［第１の実施形態］
第１の実施形態に係る溶融核燃料物質の回収方法を図１乃至図３により説明する。 Hereinafter, embodiments of a method for recovering a molten nuclear fuel material according to the present invention will be described with reference to the drawings.
[First Embodiment]
A method for recovering molten nuclear fuel material according to the first embodiment will be described with reference to FIGS.

（構成）
沸騰水型原子炉（ＢＷＲ）では、格納容器３内に圧力容器４が収容され、圧力容器４内には炉心支持板２上に複数の燃料集合体が装荷された炉心１が設置されている。過酷事故時に燃料集合体の核燃料物質が溶融すると、溶融核燃料物質５は、図１に示すように、炉心支持板２、圧力容器４の下部又は格納容器３の下部に付着する可能性がある。その他、溶融核燃料物質５は、制御棒案内管や炉心シュラウド等にも付着する可能性がある（図示せず）。
本実施形態では、炉心支持板２に付着した溶融核燃料物質５を回収する例について説明するが、他の原子炉構造物に付着した場合にも適用できることはもちろんである。 (Constitution)
In a boiling water reactor (BWR), a pressure vessel 4 is accommodated in a containment vessel 3, and a core 1 loaded with a plurality of fuel assemblies is installed on a core support plate 2 in the pressure vessel 4. . If the nuclear fuel material of the fuel assembly is melted in a severe accident, the molten nuclear fuel material 5 may adhere to the core support plate 2, the lower part of the pressure vessel 4, or the lower part of the containment vessel 3, as shown in FIG. In addition, the molten nuclear fuel material 5 may adhere to a control rod guide tube, a core shroud, or the like (not shown).
In the present embodiment, an example in which the molten nuclear fuel material 5 attached to the core support plate 2 is recovered will be described, but it is needless to say that the present invention can be applied to cases where it adheres to other nuclear reactor structures.

本実施形態の回収方法に用いられる回収装置は、図２及び図３に示すように、回収対象物に対し繰り返し衝撃荷重を加える破砕工具７と、破砕工具７により破砕された溶融核燃料物質５及び切断工具１２により切断された炉心支持板２を回収する回収工具８と、破砕工具７、回収工具８又は切断工具１２が先端に装着された昇降装置１０と、昇降装置１０を駆動制御するクレーン９と、昇降装置１０の先端に取り付けられ破砕対象物及び回収対象物を撮像するＴＶカメラ等からなる撮像装置１１と、破砕された溶融核燃料物質５を収容する容器６と、から構成される。   As shown in FIGS. 2 and 3, the recovery device used in the recovery method of the present embodiment includes a crushing tool 7 that repeatedly applies an impact load to an object to be recovered, a molten nuclear fuel material 5 crushed by the crushing tool 7, and A recovery tool 8 that recovers the core support plate 2 cut by the cutting tool 12, a lifting device 10 with a crushing tool 7, a recovery tool 8, or a cutting tool 12 attached to the tip, and a crane 9 that drives and controls the lifting device 10. And an image pickup device 11 that is attached to the tip of the lifting device 10 and includes a TV camera or the like for picking up an object to be crushed and an object to be collected, and a container 6 that contains the crushed molten nuclear fuel material 5.

破砕工具７は、例えば、溶融核燃料物質５に繰り返し衝撃荷重を付与することが可能なたがね状又は先端が鋭利な形状をしている工具刃と、工具刃を電磁力、油圧又は空気圧で往復動駆動させる駆動装置とから構成される（図示せず）。   The crushing tool 7 includes, for example, a tool blade capable of repeatedly applying an impact load to the molten nuclear fuel material 5 or a tool blade having a sharp tip, and the tool blade by electromagnetic force, hydraulic pressure or air pressure. A reciprocating drive device (not shown).

また、破砕された溶融核燃料物質５ａを回収する回収工具８としては、グラブバケット等の工具が用いられる。
なお、破砕工具７、回収工具８及び切断工具１２は昇降装置１０の先端にそれぞれ着脱可能に装着するようにしてもよいが、それぞれ専用の昇降装置１０に装着するようにしてもよい。 A tool such as a grab bucket is used as the recovery tool 8 for recovering the crushed molten nuclear fuel material 5a.
The crushing tool 7, the recovery tool 8, and the cutting tool 12 may be detachably mounted on the tip of the lifting device 10, but may be mounted on a dedicated lifting device 10.

（作用）
本実施形態は溶融核燃料物質５を原子炉構造物である炉心支持板２と分別して回収することを特徴とする。 (Function)
The present embodiment is characterized in that the molten nuclear fuel material 5 is collected separately from the core support plate 2 that is a nuclear reactor structure.

この分別回収は、回収対象物が溶融核燃料物質５である場合、当該溶融核燃料物質５は酸化ウランがいったん溶融した後固化したものであるため、セラミックスのように硬くもろく、破砕工具７による繰り返し衝撃荷重により小片に破砕されるのに対し、回収対象物が炉心支持板２である場合、当該炉心支持板２は金属製であるため破砕工具７によって一部塑性変形するものの破砕されない性質を利用する。   In this fractional collection, when the object to be recovered is the molten nuclear fuel material 5, the molten nuclear fuel material 5 is solidified after the uranium oxide is once melted. Therefore, it is hard and brittle like ceramics and is repeatedly impacted by the crushing tool 7. When the object to be recovered is the core support plate 2 while being crushed into small pieces by the load, the core support plate 2 is made of metal, and therefore, a part of the core support plate 2 that is plastically deformed by the crushing tool 7 is used. .

〈分別及び破砕工程〉
まず、破砕工具７が装着された昇降装置１０を溶融核燃料物質５が付着した炉心支持板２上に降下させ、回収対象物に対し破砕工具７により繰り返し衝撃荷重を加える（図２（ａ））。そして衝撃荷重が加えられた後の回収対象物の外観形状を撮像装置１１により観察し、回収対象物が破砕していれば溶融核燃料物質５と判定し、破砕が観察されなければ炉心支持板２と判定する。この場合、あらかじめ溶融核燃料物質５が破砕する衝撃荷重を求めておけば、当該求められた衝撃荷重を加えることによって、より明確に溶融核燃料物質５を選択的に破砕することができる。 <Separation and crushing process>
First, the lifting / lowering device 10 equipped with the crushing tool 7 is lowered onto the core support plate 2 to which the molten nuclear fuel material 5 adheres, and an impact load is repeatedly applied to the collection object by the crushing tool 7 (FIG. 2 (a)). . Then, the appearance shape of the recovery object after the impact load is applied is observed by the imaging device 11. If the recovery object is crushed, it is determined as the molten nuclear fuel material 5, and if no crushing is observed, the core support plate 2. Is determined. In this case, if the impact load at which the molten nuclear fuel material 5 is crushed is obtained in advance, the molten nuclear fuel material 5 can be selectively crushed more clearly by applying the obtained impact load.

〈回収工程〉
次に、破砕された溶融核燃料物質５ａを回収工具８によって採取し（図２（ｂ））、容器６内に収納する（図２（ｃ））。
このように、容器６には溶融核燃料物質５のみが収納されるため、再臨界管理を高精度で行うことができ、再臨界の発生を確実に防止することができる。 <Recovery process>
Next, the crushed molten nuclear fuel material 5a is collected by the collection tool 8 (FIG. 2B) and stored in the container 6 (FIG. 2C).
In this way, since only the molten nuclear fuel material 5 is stored in the container 6, recriticality management can be performed with high accuracy, and the occurrence of recriticality can be reliably prevented.

〈原子炉構造物の回収〉
一方、回収対象物が炉心支持板２と判定された場合は（図３（ａ））、昇降装置１０の先端に例えば回転鋸等からなる切断工具１２を装着し、炉心支持板２を切断する（図３（ｂ）、（ｃ））。切断された炉心支持板２ａは回収工具８によって搬出され、溶融核燃料物質５を収納する容器６とは異なる容器に収納される（図示せず）。 <Recovery of reactor structure>
On the other hand, when the recovery object is determined to be the core support plate 2 (FIG. 3A), a cutting tool 12 made of, for example, a rotary saw is attached to the tip of the lifting device 10 to cut the core support plate 2. (FIGS. 3B and 3C). The cut core support plate 2a is unloaded by the recovery tool 8 and stored in a container (not shown) different from the container 6 storing the molten nuclear fuel material 5.

なお、溶融核燃料物質５が付着した炉心支持板２や制御棒案内管等の炉心構造物は、圧力容器４の下部又は格納容器３の下部に堆積した溶融核燃料物質５の回収作業の障害となる場合や原子炉の解体作業時等に適宜切断回収される。   Note that the core structure such as the core support plate 2 and the control rod guide tube to which the molten nuclear fuel material 5 adheres becomes an obstacle to the recovery operation of the molten nuclear fuel material 5 deposited under the pressure vessel 4 or under the containment vessel 3. In some cases or when the reactor is dismantled, it is cut and collected as appropriate.

（効果）
本実施形態によれば、再臨界管理が必要な溶融核燃料物質と再臨界管理の必要がない原子炉構造物を簡便な手段で分別し、それぞれを異なる容器に回収することにより、溶融核燃料物質に対して厳格で精度の高い再臨界管理を行うことができる。 (effect)
According to the present embodiment, the molten nuclear fuel material that requires recriticality management and the reactor structure that does not require recriticality management are separated by simple means, and each is collected in different containers to obtain molten nuclear fuel material. On the other hand, strict and highly accurate recriticality management can be performed.

［第２の実施形態］
第２の実施形態に係る溶融核燃料物質の回収方法を図４により説明する。
本第２の実施形態では、溶融核燃料物質５は絶縁物のため電気電導度が低いのに対し、炉心支持板２等の炉心構造物は金属製のため電気電導度が高い性質を利用して、回収対象物が溶融核燃料物質５であるか、又は原子炉構造物であるかを判定することを特徴とする。 [Second Embodiment]
A method for recovering molten nuclear fuel material according to the second embodiment will be described with reference to FIG.
In the second embodiment, the molten nuclear fuel material 5 is an insulator and has low electrical conductivity. On the other hand, the core structure such as the core support plate 2 is made of metal and has high electrical conductivity. It is characterized in that it is determined whether the recovery object is a molten nuclear fuel material 5 or a reactor structure.

まず、昇降装置１０の先端に一対の電極１３を装着し、撮像装置１１で回収対象物を確認しながら電極１３を回収対象物に接触させて電極１３間の電流を測定する（図４（ａ））。その値が基準値以下であれば溶融核燃料物質５と判定し、基準値以上であれば炉心支持板２と判定する。   First, a pair of electrodes 13 is attached to the tip of the lifting device 10, and the current between the electrodes 13 is measured by bringing the electrode 13 into contact with the collection object while confirming the collection object with the imaging device 11 (FIG. 4 (a)). )). If the value is below the reference value, it is determined as the molten nuclear fuel material 5, and if it is above the reference value, it is determined as the core support plate 2.

電極１３は、対象物と確実に接触させるため、先端が尖った針状電極を用いることが好ましい。
溶融核燃料物質５又は炉心支持板２を判別した後の破砕工程、切断工程及び回収工程は上記第１の実施形態と同様である（図４（ｂ）、（ｃ））。 The electrode 13 is preferably a needle-like electrode with a sharp tip in order to ensure contact with the object.
The crushing process, cutting process, and recovery process after discriminating the molten nuclear fuel material 5 or the core support plate 2 are the same as in the first embodiment (FIGS. 4B and 4C).

本第２の実施形態によれば、上記第１の実施形態の作用効果に加え、溶融核燃料物質５又は原子炉構造物をより簡便に分別することができる。
上記第１及び第２の実施形態ではＢＷＲプラントについて説明したが、この溶融燃料物質回収方法はＰＷＲプラント、高速増殖炉又は再処理施設にも適用することができることはもちろんである。 According to the second embodiment, in addition to the effects of the first embodiment, the molten nuclear fuel material 5 or the nuclear reactor structure can be more easily separated.
Although the BWR plant has been described in the first and second embodiments, it is needless to say that this molten fuel material recovery method can also be applied to a PWR plant, a fast breeder reactor, or a reprocessing facility.

以上、本発明の実施形態を説明したが、この実施形態は、例として提示したものであり、発明の範囲を限定することは意図していない。この新規な実施形態は、その他の様々な形態で実施されることが可能であり、発明の要旨を逸脱しない範囲で、種々の省略、組み合わせ、置き換え、変更を行うことができる。この実施形態やその変形は、発明の範囲や要旨に含まれるとともに、特許請求の範囲に記載された発明とその均等の範囲に含まれる。   As mentioned above, although embodiment of this invention was described, this embodiment is shown as an example and is not intending limiting the range of invention. The novel embodiment can be implemented in various other forms, and various omissions, combinations, replacements, and changes can be made without departing from the spirit of the invention. This embodiment and its modifications are included in the scope and gist of the invention, and are included in the invention described in the claims and the equivalents thereof.

１…炉心、２…炉心支持板（原子炉構造物）、３…格納容器、４…圧力容器、５…溶融核燃料物質、６…容器、７…破砕工具、８…回収工具、９…クレーン、１０…昇降装置、１１…撮像装置、１２…切断工具、１３…電極。   DESCRIPTION OF SYMBOLS 1 ... Core, 2 ... Core support plate (reactor structure), 3 ... Containment vessel, 4 ... Pressure vessel, 5 ... Molten nuclear fuel material, 6 ... Container, 7 ... Crushing tool, 8 ... Recovery tool, 9 ... Crane, DESCRIPTION OF SYMBOLS 10 ... Elevating device, 11 ... Imaging device, 12 ... Cutting tool, 13 ... Electrode.

Claims (3)

溶融核燃料物質が付着した原子炉構造物から前記溶融核燃料物質と前記原子炉構造物を分別回収する溶融核燃料物質の回収方法において、
回収対象物の電気電導度を測定する工程と、前記回収対象物の電気電導度が基準値以下の場合に当該回収対象物が溶融核燃料物質と判定し、電気電導度が基準値以上の場合に原子炉構造物と判定する判定工程と、回収対象物が溶融核燃料物質と判定された場合に当該溶融核燃料物質に衝撃荷重を加え破砕する破砕工程と、前記破砕された溶融核燃料物質を回収する回収工程と、を有することを特徴とする溶融核燃料物質の回収方法。 In the method for recovering a molten nuclear fuel material, the molten nuclear fuel material and the nuclear reactor structure are separated and recovered from a nuclear reactor structure to which the molten nuclear fuel material is attached.
A step of measuring the electrical conductivity of the recovery object; and when the electrical conductivity of the recovery object is below a reference value, the recovery object is determined to be a molten nuclear fuel material, and the electrical conductivity is above the reference value A determination step for determining a nuclear reactor structure, a crushing step for applying an impact load to the molten nuclear fuel material when the recovery target is determined to be a molten nuclear fuel material, and a recovery for recovering the crushed molten nuclear fuel material And a method for recovering molten nuclear fuel material. 回収対象物が原子炉構造物と判定された場合に当該原子炉構造物を切断して回収する回収工程をさらに有することを特徴とする請求項１記載の溶融核燃料物質の回収方法。 Method for recovering molten nuclear fuel material according to claim 1 Symbol placement collection object, characterized in that it further comprises a recovery step of recovering by cutting the reactor structure when it is determined that the reactor structure. 前記回収された溶融核燃料物質と原子炉構造物をそれぞれ異なる容器に収容することを特徴とする請求項２記載の溶融核燃料物質の回収方法。 3. The method for recovering molten nuclear fuel material according to claim 2, wherein the recovered molten nuclear fuel material and the reactor structure are stored in different containers.
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