JPS61175594A - Method of storing nuclear fuel aggregate - Google Patents

Method of storing nuclear fuel aggregate

Info

Publication number
JPS61175594A
JPS61175594A JP60015388A JP1538885A JPS61175594A JP S61175594 A JPS61175594 A JP S61175594A JP 60015388 A JP60015388 A JP 60015388A JP 1538885 A JP1538885 A JP 1538885A JP S61175594 A JPS61175594 A JP S61175594A
Authority
JP
Japan
Prior art keywords
fuel
guide thimble
combustible
assembly
storage
Prior art date
Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
Pending
Application number
JP60015388A
Other languages
Japanese (ja)
Inventor
錠 裕人
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Nuclear Fuel Industries Ltd
Original Assignee
Nuclear Fuel Industries Ltd
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Application filed by Nuclear Fuel Industries Ltd filed Critical Nuclear Fuel Industries Ltd
Priority to JP60015388A priority Critical patent/JPS61175594A/en
Publication of JPS61175594A publication Critical patent/JPS61175594A/en
Pending legal-status Critical Current

Links

Classifications

    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

Landscapes

  • Monitoring And Testing Of Nuclear Reactors (AREA)
  • Feeding, Discharge, Calcimining, Fusing, And Gas-Generation Devices (AREA)

Abstract

(57)【要約】本公報は電子出願前の出願データであるた
め要約のデータは記録されません。
(57) [Summary] This bulletin contains application data before electronic filing, so abstract data is not recorded.

Description

【発明の詳細な説明】 (産業上の利用分野) この発明は燃料集合体主として加圧水型原子炉用の燃料
集合体の貯蔵法に関する。
DETAILED DESCRIPTION OF THE INVENTION (Field of Industrial Application) This invention relates to a method for storing fuel assemblies, primarily for pressurized water reactors.

(従来の技術) 加圧水型原子炉用のいわゆるキャンレスタイプの燃料集
合体At:i第2図イ、口のように多数の燃・料棒1と
制御棒用の十数本の案内シンブル管2及び中央に配置さ
れる計測装置用の一つの中空管3が正方配列され、案内
シンブル管2の下端は端栓を介して下部ノズル4に装着
され、途中は数段の格子状のスペーサ5で支持され、案
内シンブル管2の上端はキャップを施すことなく上部ノ
ズル6に取付けられておシ、原子炉内にこのような集合
体Aが百数十体装填され、運転時には案内シンブル管2
に炉本体から垂下する制御棒又はあらかじめ可燃吸収棒
集合体B(これは第3図のように案内シンブル管2と同
数で同一に配置され、内部に中性子吸収物質である炭化
硼素ペレットを充填した可燃吸収棒7の上端を方形の端
板8で結束し、コイルばね9を介して吊下げ杆10に取
付けである)を挿入して燃料の出力を制御するようにな
し、また、中空管3には定期的に計測装置を挿入して炉
の稼働状況を点検するようにしている。
(Prior art) A so-called canless type fuel assembly At:i for pressurized water reactors (Fig. 2A) A large number of fuel rods 1 like a mouth and more than ten guide thimble tubes for control rods. 2 and one hollow tube 3 for a measuring device placed in the center are arranged in a square arrangement, the lower end of the guide thimble tube 2 is attached to the lower nozzle 4 via an end plug, and several lattice-shaped spacers are arranged in the middle. 5, and the upper end of the guide thimble tube 2 is attached to the upper nozzle 6 without a cap.More than 100 such assemblies A are loaded in the reactor, and during operation, the guide thimble tube 2 is 2
The control rods hanging from the reactor body or the combustible absorption rod assembly B (this is arranged in the same number as the guide thimble tube 2 as shown in Fig. 3, and is filled with boron carbide pellets, which is a neutron absorbing material, inside) The upper ends of the combustible absorption rods 7 are tied together with a rectangular end plate 8, and a hollow tube (attached to a hanging rod 10) is inserted to control the fuel output. 3, a measuring device is periodically inserted to check the operating status of the furnace.

そして、一定の運転サイクル(一般には約1年)ごとに
定期検査のため燃料集合体Aを炉から取出し、可燃吸収
棒集合体B?挿入したものではこれを燃料集合体Aから
抜き取り、燃料集合体Aは貯蔵プール中に現在の燃料棒
の濃縮度に対する臨界性に基づいて設計施工された保管
ラック(ステンレス鋼の型材からなる枠体の中に一辺が
220n〜230酊、高ざが約5mの細長なケースを約
500」のピッチで前後左右方向に配設しである)の各
ケースに収容して保管し、一方、可燃吸収棒集合体Bは
プール中に別に設けた専用のラックにスを節約するため
可燃吸収棒を短く切断して収容箱に入れるかして保管す
るような減容化処分方法も提案されて因る。
The fuel assembly A is then taken out of the furnace for periodic inspection every certain operating cycle (generally about one year), and the combustible absorption rod assembly B? In the inserted one, it is extracted from fuel assembly A, and fuel assembly A is placed in the storage pool in a storage rack (frame made of stainless steel profiles) designed and constructed based on the criticality of the current fuel rod enrichment. The slender cases with sides of 220 to 230 meters and height of about 5 meters are arranged in the front, back, left, and right directions at a pitch of about 500 meters. A method of reducing the volume of rod assembly B has been proposed, in which the combustible absorption rods are cut into short lengths and stored in a storage box in order to save space in a dedicated rack installed separately in the pool. .

(発明が解決しようとする問題点) ところで、加圧水型の炉を用いる原子力発電所では、最
近稼働率向上の念めに長期サイクル運転(1年〜1.5
4 )に移行しつつあシ、それに伴って燃料棒の濃縮度
もこれまでの3チから4〜5優に高くなって来ている。
(Problem to be solved by the invention) By the way, nuclear power plants that use pressurized water reactors have recently begun to operate on long-term cycles (1 year to 1.5
4), and along with this, the enrichment of fuel rods has increased from the previous 3 to 4 to 5 degrees.

このような実勢からして、新燃料の保管の場合は当然な
がら、燃料集合体から可燃吸収棒集合体を分離する従来
のやり方で定期検査に備えて照射ずみの燃料集合体をこ
れまでの保管ラックに収容したとすれば、臨界管理上の
余裕が小ざくなシ安全性が低くなるところから、濃縮度
に見合った新しい保管設備を準備しなければならず甚だ
不経済であり、また可燃吸収棒集合体に関して云えば、
第1に燃料集合体の保管ラックとは別の収容場所を作る
ことけプール規模が大きくなり、第2に燃料集合体の保
管ラックを利用するやり方は、それだけ燃料集合体の収
容場所を少なくすることになり、第、36に可燃吸−5
収棒を短く切断するやり方は再使用するものには適用で
きない。
Considering this situation, when storing new fuel, it is natural to use the conventional method of separating combustible absorber rod assemblies from fuel assemblies to store irradiated fuel assemblies in preparation for periodic inspections. If they were to be stored in racks, there would be a small margin for criticality control and safety would be lowered, and new storage equipment would have to be prepared that was commensurate with the concentration, which would be extremely uneconomical. As for the rod assembly,
First, creating a storage space separate from the storage rack for fuel assemblies increases the size of the pool, and second, using storage racks for fuel assemblies reduces the storage space for fuel assemblies. Therefore, in the 36th combustible intake-5
The method of cutting the storage rod short is not applicable to items that will be reused.

そこで、この発明の目的は新しい保管設備を準備するこ
とな〈従来の設備をそのまま利用して燃料集合体を安全
に保管することができ、同時に余分なスペースを必要と
せずに可燃吸収棒集合体を適切に保管する貯蔵法を提供
することにある。
Therefore, the purpose of this invention is to make it possible to safely store fuel assemblies by using existing equipment without preparing new storage equipment, and at the same time, to store combustible absorption rod assemblies without requiring extra space. The objective is to provide a storage method for properly storing.

(問題点を解決するための手段) 上記目的のもとにこの発明は、貯蔵プール中に架設され
た保管ラックの各ケース中に、正方配列された多数の燃
料棒と十数本の案内シンブル管と一本の中空管と、それ
らの下端に位置して上記案内シンブル管に取付けた下部
ノズルと途中数段のスペーサと、上記案内シンブル管及
び中空管の上端に椴付けた上部ノズルとからなる燃料集
合体をそれぞれ収容し、各燃料集合体のすべての案内シ
ンブル管に可燃吸収棒集合体の可燃吸収棒を挿入するこ
とを特徴としている。
(Means for Solving the Problems) Based on the above object, the present invention provides a storage rack with a large number of squarely arranged fuel rods and more than ten guide thimbles in each case of a storage rack installed in a storage pool. A tube, a single hollow tube, a lower nozzle located at the lower ends thereof and attached to the guide thimble tube, several spacers in the middle, and an upper nozzle attached to the upper ends of the guide thimble tube and the hollow tube. The fuel assembly is characterized in that the combustible absorption rods of the combustible absorption rod assembly are inserted into all guide thimble tubes of each fuel assembly.

(実施例) 第1図を参照の上この発明の実施例について説明すれば
、Hは貯蔵プール中に架設された燃料集合体の保管ラッ
クで、枠体11とその枠体中に配設されたケース12か
らなるが、前記従来のものと同じくこれまでの燃料棒の
濃縮度(3%)による臨界性に基づいて設計され、枠体
11はステンレス鋼からなる縦、横ならびに斜め型材で
組立てられてお夛、またケース12は同じくステンレス
鋼製で%1辺が2201111〜2301m、高さ約5
軍の方形の細長な筒体をなし、枠体11中において約5
0011mのピッチで前後左右の方向に所要数配設され
ている。各ケース12中には、正方配列され友多数の燃
料棒11土数本の案内シンブル管2゜一本の計測装置用
の中空管3.それらの下端に位置して案内シンブル管2
に取付けた下部ノズル4゜途中数段の格子状のスペーサ
5及び案内シンブル管2の上端に結合された上部ノズル
6とからなるキャンレスタイプの燃料集合体Aがそれぞ
れ収容され、そして、それらの燃料集合体Aの十数本の
案内シンブル管2には、案内シンブル管2と同数で同一
に配量された可燃吸収棒7の上端を端板8で結束し、こ
の端板8をコイルばね9を介して吊下げ杆10に連結し
た可燃吸収棒集合体Bの可燃吸収棒7が嵌挿されている
(Embodiment) Referring to FIG. 1, an embodiment of the present invention will be described. H is a storage rack for fuel assemblies installed in a storage pool, and H is a storage rack for fuel assemblies installed in a frame 11 and inside the frame. Like the conventional case 12, it is designed based on the criticality due to the enrichment (3%) of the fuel rods, and the frame 11 is assembled with vertical, horizontal and diagonal shapes made of stainless steel. The case 12 is also made of stainless steel and has a side of 2201111~2301m and a height of about 5.
It has a military rectangular elongated cylindrical body, and has approximately 5 mm in the frame 11.
A required number of them are arranged in the front, rear, left and right directions at a pitch of 0,011 m. Inside each case 12 are a large number of fuel rods arranged in a square arrangement 11 several guide thimble tubes 2. A hollow tube for a measuring device 3. Guide thimble tubes 2 located at their lower ends
Canless type fuel assemblies A are each accommodated, each consisting of a lower nozzle 4 attached to the lower nozzle 4°, several stages of lattice-like spacers 5 in the middle, and an upper nozzle 6 connected to the upper end of the guide thimble tube 2. The upper ends of the combustible absorption rods 7, which are arranged in the same number and the same amount as the guide thimble tubes 2, are bound to the ten or more guide thimble tubes 2 of the fuel assembly A with an end plate 8, and this end plate 8 is attached to a coil spring. A combustible absorption rod 7 of a combustible absorption rod assembly B connected to a hanging rod 10 via a rod 9 is inserted.

このように保管ラックHのケース12中に収容された燃
料集合体Aのすべての案内シンブル管2には可燃吸収棒
7が挿入されているので、濃縮度の高められた長期サイ
クル運転用の燃料集合体Aの並設に伴う燃料棒1の核分
裂連鎖反応が抑制さね、多数の燃料集合体Aは未臨界の
状態に維持される。
In this way, the combustible absorption rods 7 are inserted into all the guide thimble tubes 2 of the fuel assembly A housed in the case 12 of the storage rack H, so that the fuel for long-term cycle operation with increased enrichment can be used. The nuclear fission chain reaction of the fuel rods 1 due to the juxtaposition of the assemblies A is suppressed, and a large number of the fuel assemblies A are maintained in a subcritical state.

(発明の効果) 以上のようにこの発明によれば、キャンレスタイプの燃
料集合体の貯蔵に当たり、そのすべての案内シンブル管
に可燃吸収棒集合体の可燃吸収棒を挿入して貯蔵するの
で、臨界管理上の問題が解消され、長期サイクル運転用
の濃縮度の高い燃料集合体に対しても従来の保管設備を
そのまま使用することができ、甚だ経済的であシ、また
、可燃吸収棒集合体は燃料集合体と同じ場所に収容する
ことができ、これまでのように余分なスペースを必要と
することなく、貯蔵プールや施設の大型化が防がれ、再
度の使用にも便利である等の効果を有する。
(Effects of the Invention) As described above, according to the present invention, when storing a canless type fuel assembly, the combustible absorption rods of the combustible absorption rod assembly are inserted into all the guide thimble pipes. Problems with criticality control have been resolved, and conventional storage equipment can be used as is for highly enriched fuel assemblies for long-term cycle operation, making it extremely economical. The fuel assembly can be stored in the same location as the fuel assembly, which eliminates the need for extra space and prevents the storage pool or facility from becoming larger, making it convenient for reuse. It has the following effects.

【図面の簡単な説明】[Brief explanation of the drawing]

第1図はこの発明の実施例の一部切断正面図。 第2図イは燃料集合体の正面図。 同図口はそのX−X線に沿った平面図。 第3図は可燃吸収棒集合体の正面図。 図中、1・・・燃料棒、2・・・案内シンブル管、3・
・・中空管、4・・・下部ノズル、5・・・スペーサ、
6・・・上部ノズル、7・・・可燃吸収棒、A・・・燃
料集合体、B・・・可燃吸収棒集合体、H・・・保管ラ
ック。
FIG. 1 is a partially cutaway front view of an embodiment of the invention. Figure 2A is a front view of the fuel assembly. The opening in the figure is a plan view taken along the line X-X. FIG. 3 is a front view of the combustible absorption rod assembly. In the figure, 1... fuel rod, 2... guide thimble tube, 3...
... hollow tube, 4 ... lower nozzle, 5 ... spacer,
6... Upper nozzle, 7... Combustible absorption rod, A... Fuel assembly, B... Combustible absorption rod assembly, H... Storage rack.

Claims (1)

【特許請求の範囲】[Claims] 貯蔵プール中に架設された保管ラックの各ケース中に、
正方配列された多数の燃料棒と十数本の案内シンブル管
と一本の中空管と、それらの下端に位置して上記案内シ
ンブル管に取付けた下部ノズルと途中数段のスペーサと
、上記案内シンブル管の上端に取付けた上部ノズルとか
らなる燃料集合体をそれぞれ収容し、各燃料集合体のす
べての案内シンブル管に可燃吸収棒集合体の可燃吸収棒
を挿入することを特徴とする原子燃料集合体の貯蔵法。
In each case of storage racks built into the storage pool,
A large number of squarely arranged fuel rods, more than ten guide thimble tubes, one hollow tube, a lower nozzle located at the lower end thereof and attached to the guide thimble tube, and several spacers in the middle, an upper nozzle attached to the upper end of a guide thimble tube; and a combustible absorption rod of the combustible absorption rod assembly is inserted into all the guide thimble tubes of each fuel assembly. How to store fuel assemblies.
JP60015388A 1985-01-31 1985-01-31 Method of storing nuclear fuel aggregate Pending JPS61175594A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP60015388A JPS61175594A (en) 1985-01-31 1985-01-31 Method of storing nuclear fuel aggregate

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP60015388A JPS61175594A (en) 1985-01-31 1985-01-31 Method of storing nuclear fuel aggregate

Publications (1)

Publication Number Publication Date
JPS61175594A true JPS61175594A (en) 1986-08-07

Family

ID=11887355

Family Applications (1)

Application Number Title Priority Date Filing Date
JP60015388A Pending JPS61175594A (en) 1985-01-31 1985-01-31 Method of storing nuclear fuel aggregate

Country Status (1)

Country Link
JP (1) JPS61175594A (en)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US6327321B1 (en) * 1998-11-20 2001-12-04 Framatome Anp, Inc. Borated aluminum rodlets for use in spent nuclear fuel assemblies
JP2008524515A (en) * 2005-02-23 2008-07-10 エルジー エレクトロニクス インコーポレイティド Variable capacity rotary compressor

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US6327321B1 (en) * 1998-11-20 2001-12-04 Framatome Anp, Inc. Borated aluminum rodlets for use in spent nuclear fuel assemblies
JP2008524515A (en) * 2005-02-23 2008-07-10 エルジー エレクトロニクス インコーポレイティド Variable capacity rotary compressor

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