JPH02296190A - Nuclear fuel assembly - Google Patents

Nuclear fuel assembly

Info

Publication number
JPH02296190A
JPH02296190A JP1115171A JP11517189A JPH02296190A JP H02296190 A JPH02296190 A JP H02296190A JP 1115171 A JP1115171 A JP 1115171A JP 11517189 A JP11517189 A JP 11517189A JP H02296190 A JPH02296190 A JP H02296190A
Authority
JP
Japan
Prior art keywords
end plug
fuel element
insertion hole
hole
core water
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
JP1115171A
Other languages
Japanese (ja)
Inventor
Satoru Hirayama
悟 平山
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.)
Nippon Nuclear Fuel Development Co Ltd
Original Assignee
Nippon Nuclear Fuel Development Co 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 Nippon Nuclear Fuel Development Co Ltd filed Critical Nippon Nuclear Fuel Development Co Ltd
Priority to JP1115171A priority Critical patent/JPH02296190A/en
Publication of JPH02296190A publication Critical patent/JPH02296190A/en
Pending legal-status Critical Current

Links

Classifications

    • 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

Landscapes

  • Fuel-Injection Apparatus (AREA)

Abstract

PURPOSE:To achieve a higher working efficiency with safe and easier disassembling work by inserting upper end plugs of a plurality of nuclear fuel elements into a plurality of upper end plug holes provided in an upper tie plate. CONSTITUTION:A plurality of core water flow holes 11 are formed at a top of an insertion hole 8 for an upper end plug of a corner fuel element so that a core water infiltrating at the insertion hole 8 and a gap of an upper end plug 3 of the fuel element 2 flows out of a passage hole 11. The arrangement of the plurality of passage holes 11 allows a core water entering from one of the passage hole 11 to flow out of the other passage hole 11 so that the core water infiltrating into the insertion hole 8 will not retain because the core water is provided with a flow created. This permits inflow of the core water with a density of impurities always controlled to a gap between the insertion hole 8 of the fuel element 2 and an end plug 3 of the fuel element 2 thereby preventing sticking due to corrosion with the suppression of electrochemical corrosion.

Description

【発明の詳細な説明】 [産業上の利用分野] 本発明は、軽水炉の核燃料集合体に係り、特に原子力発
電所あるいは、照射後記3カ施設等の放射線管理区域に
おいて、遠隔操作により、上部タイプレートを円滑に取
外すのに好適な核燃料集合体に関するものである。
[Detailed Description of the Invention] [Industrial Application Field] The present invention relates to nuclear fuel assemblies for light water reactors, and in particular in radiation control areas such as nuclear power plants or the three irradiation facilities mentioned below, by remote control. The present invention relates to a nuclear fuel assembly suitable for smoothly removing a fuel plate.

[従来の技術] 従来の核燃料集合体の上部タイプレート上部および核燃
料集合体の解体手順について第2図および第3図を用い
て説明する。
[Prior Art] A conventional upper tie plate upper part of a nuclear fuel assembly and a procedure for disassembling the nuclear fuel assembly will be described with reference to FIGS. 2 and 3.

第2図は核燃料集合体の断面略示図、第3図は従来の上
部タイプレートと燃料要素上部端栓との嵌合説明図であ
る。
FIG. 2 is a schematic cross-sectional view of a nuclear fuel assembly, and FIG. 3 is an explanatory view of the fitting of a conventional upper tie plate and a fuel element upper end plug.

第2図の構成は、1は、上部タイプレート、2は、燃料
要素、3は、燃料要素上部端栓、4は燃料要素を保持す
るスペーサ、5は、下部タイプレート、6は、チャンネ
ルボックス、7は、タイロッド・ナツトである。
The configuration of FIG. 2 is as follows: 1: upper tie plate, 2: fuel element, 3: fuel element upper end plug, 4: spacer for holding the fuel element, 5: lower tie plate, 6: channel box , 7 is a tie rod nut.

第3図の構成は、1〜3は、第2図と同一であり、8は
、コーナ燃料要素端栓用挿入孔、9は、通水孔、10は
、通常燃料要素端栓用挿入孔である。
The configuration of FIG. 3 is as follows: 1 to 3 are the same as those in FIG. 2, 8 is an insertion hole for a corner fuel element end plug, 9 is a water passage hole, and 10 is an insertion hole for a normal fuel element end plug. It is.

つぎに、燃料集合体の解体手順について説明する。Next, the procedure for disassembling the fuel assembly will be explained.

原子炉内で使用した燃料集合体を、核燃料要素単位で検
査する場合には、第2図において、まずタイロッドナツ
ト7を取外し、上部タイプレート1を取外す。次に、核
燃料要素2の上部端栓3をトング等で掴み上方へ吊上げ
て燃料集合体から順次、引抜いていく。この場合、従来
の上部タイプレートでは、原子炉内で使用中に、第3図
に示す上部タイプレート1のコーナ燃料要素端栓用挿入
孔8と燃料要素上部端栓3との接触面が腐食し固着する
ことがあった。この固着により」二部タイプレート1の
取外しが不可能となり、燃料要素毎に検査ができない場
合があった。この腐食の原因は。
When inspecting a fuel assembly used in a nuclear reactor in units of nuclear fuel elements, as shown in FIG. 2, first the tie rod nut 7 is removed and then the upper tie plate 1 is removed. Next, the upper end plug 3 of the nuclear fuel element 2 is grasped with tongs or the like and lifted upward, and successively pulled out from the fuel assembly. In this case, in the conventional upper tie plate, during use in a nuclear reactor, the contact surface between the corner fuel element end plug insertion hole 8 of the upper tie plate 1 and the fuel element upper end plug 3 shown in FIG. 3 corrodes. Sometimes it stuck. Due to this sticking, it became impossible to remove the two-part tie plate 1, and it was sometimes impossible to inspect each fuel element. What is the cause of this corrosion?

タイプレート1の材質が不銹鋼であり、燃料要素上部端
栓3の材質がジルコニウム基合金であるため、異種金属
による電極反応による腐食、@気化学的腐食などが考え
られている。上部タイプレートと燃料要素端栓が固着す
る箇所は、上述のコーナ燃料要素端栓用挿入孔8と燃料
要素上部端栓3との接触面であり、通常燃料要素端栓用
挿入孔180での固着はみられなかった。コーナ燃料要
素端栓用挿入孔8と通常燃料要素端栓挿入孔10との違
いは、第3図で明らかなように、コーナ燃料要素端栓用
挿入孔8は貫通孔ではないことである。
Since the material of the tie plate 1 is stainless steel and the material of the fuel element upper end plug 3 is a zirconium-based alloy, corrosion due to electrode reactions caused by dissimilar metals, @gas chemical corrosion, etc. are considered. The place where the upper tie plate and the fuel element end plug are fixed is the contact surface between the above-mentioned corner fuel element end plug insertion hole 8 and the fuel element upper end plug 3, and is usually the contact surface of the fuel element end plug insertion hole 180. No adhesion was observed. The difference between the corner fuel element end plug insertion hole 8 and the normal fuel element end plug insertion hole 10 is that the corner fuel element end plug insertion hole 8 is not a through hole, as is clear from FIG.

したがって、コーナ燃料要素端栓用挿入孔8に燃料要素
上部端栓3を挿入すると当該挿入孔8内に閉じ込められ
た原子炉の冷却水(炉水)中の不純物濃度が高くなり、
電気化学的腐食を起す原因となった。また5当該孔には
通水孔9を形成した例も見られたが、通水孔の直径が小
さく、またjli −孔であるため、通水効果が小さく
、腐食防止には役立たなかった。一方、通常燃料要素端
栓用挿入孔10は貫通孔であるため、原子炉の冷却水が
常に流通して当該孔内に閉じ込められることはないため
、腐食による固着は見られなかった。
Therefore, when the fuel element upper end plug 3 is inserted into the corner fuel element end plug insertion hole 8, the impurity concentration in the reactor cooling water (reactor water) confined within the insertion hole 8 increases.
This caused electrochemical corrosion. In addition, there were some examples in which a water passage hole 9 was formed in the hole 5, but since the diameter of the water passage hole was small and it was a jli-hole, the water passage effect was small and it was not useful for corrosion prevention. On the other hand, since the insertion hole 10 for the normal fuel element end plug is a through hole, the cooling water of the reactor always flows through and is not confined within the hole, so no fixation due to corrosion was observed.

いま、燃料集合体を解体して上部タイプレートを取外す
際に、上記のように腐食による固着状態が生じると、燃
料要素単体での検査が不可能になる場合がある。また、
固着を解除するには、特殊な装百が必要となり、安全で
、確実に解体することができる構造の燃料集合体の製作
が望まれていた。
Now, when the fuel assembly is disassembled and the upper tie plate is removed, if a stuck state due to corrosion occurs as described above, it may become impossible to inspect the fuel element alone. Also,
To release the fixation, special equipment is required, and it has been desired to create a fuel assembly that is safe and can be dismantled reliably.

従来型の核燃料集合体の場合に固着状態から燃料要素を
引抜く方法として下部タイプレートを加熱して、熱膨張
法を利用する方法として特開昭60−202394号公
報が提案されているが、この方法が上部タイプレートの
取外しに応用可能と考えられる。
In the case of a conventional nuclear fuel assembly, Japanese Patent Application Laid-Open No. 60-202394 proposes a method of heating the lower tie plate and utilizing a thermal expansion method to pull out the fuel element from the stuck state. It is believed that this method can be applied to the removal of the upper tie plate.

[発明が解決しようとする課題] 上記従来技術は、熱膨張差を利用した1つの改良された
方法であるが、プール内(水中)のような特殊な環境下
で、この方法を実施しようとすると、加熱に要する諸設
備費およびその労務費、さらに作業効率の点で問題があ
った。
[Problems to be Solved by the Invention] The above-mentioned prior art is an improved method that utilizes the difference in thermal expansion, but it is difficult to implement this method in a special environment such as inside a pool (underwater). This caused problems in terms of equipment costs and labor costs required for heating, as well as work efficiency.

本発明の目的は、燃料集合体から上部タイプレートを取
外す際に、燃料要素上部端栓の挿入孔と燃料要素上部端
栓の腐食による固着を防止し、解体作業を安全かつ、容
易にし1作業効率の向上をはかることができる燃料集合
体を提供することである。
An object of the present invention is to prevent the insertion hole of the fuel element upper end plug and the fuel element upper end plug from sticking due to corrosion when removing the upper tie plate from the fuel assembly, thereby making the disassembly work safe and easy. An object of the present invention is to provide a fuel assembly capable of improving efficiency.

[課題を解決するための手段] 上記課題を解決するための本発明に係る核燃料集合体の
構成は、上部および下部端栓を有する複数本の核燃料要
素の上部端栓を、上部タイプレートに設けられた複数個
の上部端栓孔に挿入することにより、これら核燃料要素
の上端部を保持してなり、これら複数個の上部端栓孔の
一部は、その上端が不貫通構造であるものにおいて、上
記不貫通孔構造である上部端栓孔の上部に、炉水流通用
の複数個の小孔を設けるようにしたことである。
[Means for Solving the Problems] In order to solve the above problems, the structure of the nuclear fuel assembly according to the present invention is such that the upper end plugs of a plurality of nuclear fuel elements having upper and lower end plugs are provided on the upper tie plate. The upper ends of these nuclear fuel elements are held by inserting them into a plurality of upper end plug holes, and some of these upper end plug holes have a non-penetrating structure. , a plurality of small holes for reactor water circulation are provided above the upper end plug hole having the non-through-hole structure.

[作用コ 燃料集合体において、上部タイプレートのコーナ燃料要
素の上部端栓用挿入孔先端部に複数個の炉水流通孔を形
成したことは、原子炉内で長期間使用しても、端栓挿入
孔内に常時、不純物のコントロールされた原子炉冷却水
が循環して流通するため、不純物の滞留がなく端栓挿入
孔と燃料要素上部端の接触部に生じ易い電気化学的腐食
を抑制することができるので、固着状態を防止すること
ができる。
[In the working co-fuel assembly, a plurality of reactor water flow holes are formed at the tip of the upper end plug insertion hole of the corner fuel element of the upper tie plate. Because reactor cooling water with controlled impurities is constantly circulated in the plug insertion hole, there is no accumulation of impurities, and electrochemical corrosion that tends to occur at the contact area between the end plug insertion hole and the upper end of the fuel element is suppressed. Therefore, a stuck state can be prevented.

[実施例] 以下1本発明の実施例を第1図を用いて説明する。[Example] An embodiment of the present invention will be described below with reference to FIG.

第1図は1本発明の実施例に係り、炉水流通孔の説明図
である。
FIG. 1 is an explanatory diagram of a reactor water flow hole according to an embodiment of the present invention.

第1図の構成において、11は、炉水流通孔である。な
お、1〜3,8および10は第2〜3図に示したものと
同一である。
In the configuration shown in FIG. 1, 11 is a reactor water flow hole. Note that 1 to 3, 8, and 10 are the same as those shown in FIGS. 2 and 3.

第1図を用いて実施例をさらに詳細に説明すると、同図
は、上部タイプレート1の構造を示すもので、コーナ燃
料要素上部端栓用挿入孔8の頂部に、直径3mの複数個
の炉水流通孔11を形成し、該挿入孔と燃料要素2の上
部端栓3のギャップから浸入する炉水は、炉水流通孔1
1がら流出する。
The embodiment will be explained in more detail with reference to FIG. 1. The figure shows the structure of the upper tie plate 1, in which a plurality of 3 m diameter holes are installed at the top of the insertion hole 8 for the corner fuel element upper end plug. A reactor water flow hole 11 is formed, and the reactor water that enters through the gap between the insertion hole and the upper end plug 3 of the fuel element 2 flows through the reactor water flow hole 1.
1 will flow out.

また、炉水流通孔11を、複数個設けたことにより、一
方の炉水流通孔11より入った炉水は、他の炉水流通孔
11より流出するため、該挿入孔8に浸入した炉水に流
れができて、滞留することがない。
Furthermore, by providing a plurality of reactor water flow holes 11, the reactor water that entered through one reactor water flow hole 11 flows out from the other reactor water flow hole 11. Water flows and does not stagnate.

このように、該挿入孔8に浸入した炉水は、炉水流通孔
11から流出するため、コーナ燃料要素の端栓用挿入孔
8とコーナ燃料要素の上部端栓3とのギャップには常時
、不純物濃度がコントロールされた炉水が流入するため
電気化学的腐食を抑制することができ、腐食による固着
を防止する効果がある。
In this way, since the reactor water that has entered the insertion hole 8 flows out from the reactor water flow hole 11, there is always a gap between the end plug insertion hole 8 of the corner fuel element and the upper end plug 3 of the corner fuel element. Since reactor water with a controlled impurity concentration flows in, electrochemical corrosion can be suppressed, which has the effect of preventing sticking due to corrosion.

[発明の効果] 本発明によれば、つぎのような効果が得られる。[Effect of the invention] According to the present invention, the following effects can be obtained.

(1)上部タイプレートのコーナ燃料要素端栓挿入孔の
頂部に複数個の小孔を設けることにより、上記端栓挿入
孔と上部端栓との間に浸入する炉水の流通がよくなり、
腐食が生じないため、固着することがなくなった。
(1) By providing a plurality of small holes at the top of the corner fuel element end plug insertion hole of the upper tie plate, the flow of reactor water that enters between the end plug insertion hole and the upper end plug is improved;
Since no corrosion occurs, it no longer sticks.

(2)したがって、核燃料集合体の解体にあたり、核燃
料要素を取出す前に、上部タイプレートを取外す作業が
容易に行なわれるようになった。
(2) Therefore, when disassembling a nuclear fuel assembly, the upper tie plate can be easily removed before taking out the nuclear fuel elements.

(3)核燃料集合体の解体作業が、安全に、確実に行な
われるようになったので、解体作業効率は向上し、経済
性の向上にも効果があった。
(3) Since the dismantling work of nuclear fuel assemblies can now be carried out safely and reliably, the efficiency of the dismantling work has improved and has also had the effect of improving economic efficiency.

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

第1図は、本発明に係る実施例の上部タイプレートの端
栓挿入孔の説明図、第2図は、従来例の核燃料集合体の
部分断面略示図、第3図派は、従来の上部タイプレート
の端栓挿入孔の説明図である。 〈符号の説明〉 1・・・上部タイプレート、2核燃料要素、3核燃料要
素上部端栓、4・・・スペーサ、5・・・下部タイプレ
ート、6・・・チャンネルボックス、7・・・タイロッ
ドナツト、8・・・コーナ燃料要素上部端栓用挿入孔、
9・・・通水孔、10・・・通常燃料要素上部端栓用挿
入孔、11・・・炉水流通孔。
FIG. 1 is an explanatory view of the end plug insertion hole of the upper tie plate of the embodiment according to the present invention, FIG. It is an explanatory view of an end plug insertion hole of an upper tie plate. <Explanation of symbols> 1... Upper tie plate, 2... Nuclear fuel element, 3... Nuclear fuel element upper end plug, 4... Spacer, 5... Lower tie plate, 6... Channel box, 7... Tie rod Nut, 8... Corner fuel element upper end plug insertion hole;
9... Water passage hole, 10... Normal fuel element upper end plug insertion hole, 11... Reactor water circulation hole.

Claims (1)

【特許請求の範囲】 1、上部および下部端栓を有する複数本の核燃料要素の
上部端栓を、上部タイプレートに設けられた複数個の上
部端栓孔に挿入することにより、これら核燃料要素の上
端部を保持してなり、これら複数個の上部端栓孔の一部
は、その上端が不貫通構造であるものにおいて、上記不
貫通孔構造である上部端栓孔の上部に、炉水流通用の複
数個の小孔を設けたことを特徴とする核燃料集合体。 2、請求項1において、上記不貫通孔構造を有する上部
端栓孔が、上記上部タイプレートの四隅に設けられてい
ることを特徴とする核燃料集合体。
[Claims] 1. By inserting the upper end plugs of a plurality of nuclear fuel elements having upper and lower end plugs into the plurality of upper end plug holes provided in the upper tie plate, the nuclear fuel elements can be In the case where some of the plurality of upper end plug holes have an impenetrable structure at their upper ends, a hole for reactor water circulation is provided above the upper end plug hole having the impermeable structure. A nuclear fuel assembly characterized by having a plurality of small holes. 2. The nuclear fuel assembly according to claim 1, wherein the upper end plug holes having the impermeable hole structure are provided at the four corners of the upper tie plate.
JP1115171A 1989-05-10 1989-05-10 Nuclear fuel assembly Pending JPH02296190A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP1115171A JPH02296190A (en) 1989-05-10 1989-05-10 Nuclear fuel assembly

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP1115171A JPH02296190A (en) 1989-05-10 1989-05-10 Nuclear fuel assembly

Publications (1)

Publication Number Publication Date
JPH02296190A true JPH02296190A (en) 1990-12-06

Family

ID=14656104

Family Applications (1)

Application Number Title Priority Date Filing Date
JP1115171A Pending JPH02296190A (en) 1989-05-10 1989-05-10 Nuclear fuel assembly

Country Status (1)

Country Link
JP (1) JPH02296190A (en)

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2009058505A (en) * 2007-08-31 2009-03-19 Global Nuclear Fuel Americas Llc Method for filtering debris shields and debris for upper tie plates in nuclear fuel bundles
JP2009058506A (en) * 2007-08-31 2009-03-19 Global Nuclear Fuel Americas Llc Debris shield upper tie plate for nuclear fuel assembly and method to shield assembly from debris
JP2011047939A (en) * 2009-08-28 2011-03-10 Global Nuclear Fuel Americas Llc Debris mitigation upper tie plates and fuel bundles using the same

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2009058505A (en) * 2007-08-31 2009-03-19 Global Nuclear Fuel Americas Llc Method for filtering debris shields and debris for upper tie plates in nuclear fuel bundles
JP2009058506A (en) * 2007-08-31 2009-03-19 Global Nuclear Fuel Americas Llc Debris shield upper tie plate for nuclear fuel assembly and method to shield assembly from debris
JP2011047939A (en) * 2009-08-28 2011-03-10 Global Nuclear Fuel Americas Llc Debris mitigation upper tie plates and fuel bundles using the same

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