JP3137558B2 - Inspection table and inspection method for inserts in reactor fuel assemblies - Google Patents
Inspection table and inspection method for inserts in reactor fuel assembliesInfo
- Publication number
- JP3137558B2 JP3137558B2 JP07143482A JP14348295A JP3137558B2 JP 3137558 B2 JP3137558 B2 JP 3137558B2 JP 07143482 A JP07143482 A JP 07143482A JP 14348295 A JP14348295 A JP 14348295A JP 3137558 B2 JP3137558 B2 JP 3137558B2
- Authority
- JP
- Japan
- Prior art keywords
- inspection
- fuel assembly
- reactor fuel
- control rod
- simulated
- 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.)
- Expired - Lifetime
Links
- 238000007689 inspection Methods 0.000 title claims description 43
- 239000003758 nuclear fuel Substances 0.000 title claims description 21
- 238000000034 method Methods 0.000 title claims description 7
- 230000000712 assembly Effects 0.000 title description 3
- 238000000429 assembly Methods 0.000 title description 3
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 8
- 230000005855 radiation Effects 0.000 claims description 4
- 239000000446 fuel Substances 0.000 description 15
- 239000002574 poison Substances 0.000 description 9
- 231100000614 poison Toxicity 0.000 description 9
- 239000008358 core component Substances 0.000 description 3
- 102200052313 rs9282831 Human genes 0.000 description 3
- 230000003028 elevating effect Effects 0.000 description 2
- 241000239290 Araneae Species 0.000 description 1
- 230000005540 biological transmission Effects 0.000 description 1
- 238000007796 conventional method Methods 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 230000004907 flux Effects 0.000 description 1
- 230000000737 periodic effect Effects 0.000 description 1
- 230000009257 reactivity Effects 0.000 description 1
- 238000011179 visual inspection Methods 0.000 description 1
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
- Monitoring And Testing Of Nuclear Reactors (AREA)
Description
【発明の詳細な説明】DETAILED DESCRIPTION OF THE INVENTION
【0001】[0001]
【産業上の利用分野】本発明は、原子炉内で使用される
非核燃料炉心構成品の検査装置及び検査方法に関する。BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to an apparatus and method for inspecting non-nuclear fuel core components used in a nuclear reactor.
【0002】[0002]
【従来の技術】例えば、加圧水型原子炉では、制御棒ク
ラスタ、可燃性毒物棒集合体、シンブルプラグアセンブ
リといった非核燃料炉心構成品が原子炉燃料集合体に挿
入されて使用されている。これらの構造を簡単に説明す
ると、制御棒クラスタは、図9に示すように、多数の細
長い制御棒2が、それぞれスパイダアーム3を介してハ
ブ4に固定されて房状に形成されている。制御棒クラス
タ1は、制御棒2が、原子炉燃料集合体の制御棒案内管
に各別に挿入されて使用され、中性子を吸収して炉心の
反応度を制御するものである。2. Description of the Related Art For example, in a pressurized water reactor, non-nuclear fuel core components such as a control rod cluster, a burnable poison rod assembly, and a thimble plug assembly are inserted into a reactor fuel assembly and used. Briefly describing these structures, as shown in FIG. 9, the control rod cluster has a large number of elongated control rods 2 fixed to a hub 4 via spider arms 3 to form a tuft. In the control rod cluster 1, control rods 2 are used separately inserted into control rod guide tubes of a reactor fuel assembly to absorb neutrons and control the reactivity of the core.
【0003】シンブルプラグアセンブリは、図10に示
すように、多数のシンブルプラグ6を取付け板7に垂下
固定し、中央上部にホルダ8が設けられている。原子炉
炉心内に装荷される百体以上の燃料集合体は、同一の機
械的構造を持っているが、すべての燃料集合体に必ずし
も同時には制御棒クラスタ1が使用される訳ではないの
で、制御棒クラスタ1が使用されない原子炉燃料集合体
では、その制御棒案内管が空いた状態になる。シンブル
プラグアセンブリ5は、そのような燃料集合体の不使用
制御棒案内管を実質的に塞ぐために使用されるものであ
る。As shown in FIG. 10, the thimble plug assembly has a large number of thimble plugs 6 hanging down and fixed to a mounting plate 7, and a holder 8 provided at the upper center. Although more than one hundred fuel assemblies loaded into the reactor core have the same mechanical structure, the control rod cluster 1 is not necessarily used for all fuel assemblies at the same time. In a reactor fuel assembly in which the control rod cluster 1 is not used, the control rod guide tube is in an empty state. The thimble plug assembly 5 is used to substantially close the unused control rod guide tube of such a fuel assembly.
【0004】可燃性毒物棒集合体(バーナブルポイズン
アセンブリ)は、図11に示すように、シンブルプラグ
アセンブリ5の一部のシンブルプラグ6を可燃性毒物棒
11で置換したもので、このような可燃性毒物棒集合体
9は、炉心内の中性子束分布を整えるために主として使
用されるものである。このような非核燃料炉心構成品
は、燃料集合体に挿入して使用されるので所謂燃料集合
体内挿物として総称される。これらの内挿物は、炉心内
で使用されるので、定期的な検査が安全な原子炉運転の
ために必要とされている。As shown in FIG. 11, a burnable poison stick assembly (burnable poison assembly) is obtained by replacing a part of a thimble plug 6 of a thimble plug assembly 5 with a burnable poison stick 11. The burnable poison rod assembly 9 is mainly used for adjusting the neutron flux distribution in the core. Since such non-nuclear fuel core components are used by being inserted into the fuel assembly, they are generally referred to as so-called fuel assembly inserts. Since these inserts are used in the reactor core, periodic inspections are needed for safe reactor operation.
【0005】このような内挿物の検査の仕方を制御棒ク
ラスタ1の場合を例にして説明すると、図12において
燃料検査ピット13の放射線遮蔽水15の中に、制御棒
クラスタ1を取扱工具17を介してクレーン18により
吊り下げる。そして昇降機構を介して吊り下げられた水
中テレビカメラ19を制御棒クラスタ1の外面に沿って
昇降し、制御棒クラスタ1の外観を検査する。A method of inspecting such an inserted object will be described by taking the control rod cluster 1 as an example. In FIG. 12, the control rod cluster 1 is placed in the radiation shielding water 15 of the fuel inspection pit 13 by using a tool. It is suspended by a crane 18 via 17. Then, the underwater television camera 19 suspended via the elevating mechanism is moved up and down along the outer surface of the control rod cluster 1, and the appearance of the control rod cluster 1 is inspected.
【0006】[0006]
【発明が解決しようとする課題】前述のように制御棒ク
ラスタ等を水中に吊り下げた状態で外観検査を行うと、
水の屈折率が大きいから少しでも横揺れしていると、正
確な検査ができない。したがって、横揺れ停止を待つ時
間が長くなり、検査に長い時間を要することになる。
又、テレビカメラの操作要員とクレーン操作要員が同時
に必要であり、内挿物の検査位置への設定に時間を要
し、又検査中はクレーンが占有されて他の作業ができな
いなどといったことから全体としての作業効率が悪かっ
た。従って、本発明は、原子炉燃料集合体内挿物の外観
検査を効率的に行える装置及び方法を提供することを目
的とする。As described above, when the appearance inspection is performed while the control rod clusters and the like are suspended in the water,
Since the water has a large refractive index, it cannot be accurately inspected if it slightly sways. Therefore, the time to wait for the roll stop is lengthened, and the inspection takes a long time.
In addition, TV camera operating personnel and crane operating personnel are required at the same time, it takes time to set the insert to the inspection position, and the crane is occupied during the inspection and other operations can not be performed. Work efficiency as a whole was poor. Accordingly, an object of the present invention is to provide an apparatus and a method that can efficiently perform an appearance inspection of an insert in a reactor fuel assembly.
【0007】[0007]
【課題を解決するための手段】かかる目的を達成するた
め、本発明によれば、原子炉燃料集合体内挿物の検査に
用いられる装置としての検査台は、原子炉燃料集合体の
上部ノズル及び下部ノズルをそれぞれ模擬する模擬上部
ノズル及び模擬下部ノズル、前記両模擬ノズルを前記原
子炉燃料集合体を模擬して相互に連結する支柱、及び前
記支柱の中間部に配置され前記原子炉燃料集合体の制御
棒案内管を模擬する案内管を備えた中間胴から成ってい
る。更に本発明の検査方法によれば、放射線遮蔽水中に
設けた回転テーブルの上に前述のような検査台を載置
し、原子炉燃料集合体内挿物をその検査台の模擬上部ノ
ズルに挿入保持し、前記回転テーブルを回転しつつ該内
挿物の外面がテレビカメラにより走査される。According to the present invention, there is provided, in accordance with the present invention, an inspection table as an apparatus used for inspecting inserts in a reactor fuel assembly, comprising: an upper nozzle of the reactor fuel assembly; A simulated upper nozzle and a simulated lower nozzle that respectively simulate a lower nozzle, a column connecting the both simulated nozzles to each other by simulating the reactor fuel assembly, and the reactor fuel assembly disposed at an intermediate portion of the column. Of the control rod guide tube. Further, according to the inspection method of the present invention, the inspection table as described above is placed on a rotary table provided in radiation shielding water, and the insert in the reactor fuel assembly is inserted and held in the simulated upper nozzle of the inspection table. The outer surface of the insert is scanned by a television camera while rotating the rotary table.
【0008】[0008]
【作用】如上の構成の検査台は、制御棒クラスタ、シン
ブルプラグアセンブリ、可燃性毒物棒集合体といった内
挿物が実際に使用される原子炉燃料集合体を模擬してお
り、その模擬上部ノズルがそのような内挿物を安定的に
支持し、中間胴の案内管が、制御棒クラスタの制御棒、
可燃性毒物棒集合体の可燃性毒物棒を横方向に支持し、
上下の支柱部で、被検査部を露出し、検査を可能にす
る。上述のような検査台を放射線遮蔽水中の回転テーブ
ルに載せることにより、周方向固定のテレビカメラに対
し内挿物の被検査外面を対向せしめる。The inspection table having the above structure simulates a nuclear fuel assembly in which an insert such as a control rod cluster, a thimble plug assembly, and a burnable poison rod assembly is actually used. Stably supports such an insert, and the guide tube of the intermediate cylinder is the control rod of the control rod cluster,
Laterally supporting the burnable poison sticks of the burnable poison stick assembly,
The part to be inspected is exposed by the upper and lower struts to enable the inspection. By mounting the inspection table as described above on the rotary table in the radiation-shielded water, the outer surface to be inspected of the insert is opposed to the television camera fixed in the circumferential direction.
【0009】[0009]
【実施例】以下添付の図面を参照して本発明の実施例を
説明する。図1を参照するに、検査台20の模擬上部ノ
ズル21は、図示しない原子炉燃料集合体の上部ノズル
を模擬したもので、特に外形や内挿物が挿入される部分
(穴23を含む)は、完全に形状、寸法を一致させてい
るが、ホールドダウン用ばね等の取り付け部など直接的
に関係のない部分は、適宜概略構造になっている。同様
に燃料集合体の下部ノズルを模擬する模擬下部ノズル2
5が設けられ、これら両ノズル21,25の相対関係
が、燃料集合体のそれを模擬するように、上方支柱2
7、下方支柱29及び中間胴31によって連結されてい
る。支柱27,29は、図からもよく分かる様に、ノズ
ル21,25の四隅に位置するようにそれぞれ連結され
ている。これらの構造は、図2、図3、図4及び図5に
更に明確に示されている。Embodiments of the present invention will be described below with reference to the accompanying drawings. Referring to FIG. 1, a simulated upper nozzle 21 of an inspection table 20 simulates an upper nozzle of a reactor fuel assembly (not shown), and particularly includes a portion (including a hole 23) into which an outer shape or an insert is inserted. Although the shape and dimensions are completely matched, the parts not directly related, such as the attachment part such as a hold-down spring, are appropriately structured as appropriate. Similarly, a simulated lower nozzle 2 simulating the lower nozzle of the fuel assembly
5 are provided, and the upper column 2 is provided so that the relative relationship between the two nozzles 21 and 25 simulates that of the fuel assembly.
7, are connected by the lower support 29 and the intermediate body 31. The supports 27 and 29 are connected so as to be located at the four corners of the nozzles 21 and 25, respectively, as can be clearly understood from the drawing. These structures are more clearly shown in FIGS. 2, 3, 4 and 5.
【0010】図2及び図3に示すように、模擬上部ノズ
ル21は、燃料集合体の上部ノズルと外形形状寸法が同
じであると共に、制御棒クラスタ1の制御棒2の挿通さ
れる穴23が形成され、図示しない燃料集合体取扱工具
に係合するときに用いられる位置決め穴22が対角位置
にある隅上面に形成されている。このように、模擬上部
ノズル21は、外形形状寸法と位置決め穴が完全に模擬
されているので、上方から接近する燃料集合体取扱工具
によって確りと把持され得る。図2及び図4に示すよう
に、中間胴31には前述の穴23に整列して案内管33
が配置され、その上下端が上板35及び下板37に固定
されている。下板37及び上板35は、中央の円柱39
及び隅部の側枠41により互いに連結されている。これ
らの案内管33には、制御棒2や可燃性毒物棒11が挿
通される。更に、模擬下部ノズル25は、図2及び図5
に示すように、燃料集合体の下部ノズルの外形寸法及び
炉心板上に装荷するときの脚部の位置決め穴43を模擬
している。この位置決め穴43は、後述するように検査
を実施する際に回転テーブル45上に検査台20をセッ
トするときに使用される。As shown in FIGS. 2 and 3, the simulated upper nozzle 21 has the same outer shape and dimensions as the upper nozzle of the fuel assembly, and has a hole 23 through which the control rod 2 of the control rod cluster 1 is inserted. A positioning hole 22 formed and used when engaging with a fuel assembly handling tool (not shown) is formed on the upper surface of a corner at a diagonal position. In this manner, the simulated upper nozzle 21 is completely simulated with the outer shape and dimensions and the positioning holes, and thus can be securely gripped by the fuel assembly handling tool approaching from above. As shown in FIGS. 2 and 4, the guide tube 33 is aligned with the hole 23 in the intermediate cylinder 31.
Are arranged, and the upper and lower ends thereof are fixed to the upper plate 35 and the lower plate 37. The lower plate 37 and the upper plate 35 have a central column 39.
And are connected to each other by side frames 41 at the corners. The control rod 2 and the burnable poison rod 11 are inserted through these guide tubes 33. Further, the simulated lower nozzle 25 is shown in FIGS.
As shown in Fig. 7, the outer dimensions of the lower nozzle of the fuel assembly and the positioning holes 43 of the legs when loading the core on the core plate are simulated. The positioning holes 43 are used when setting the inspection table 20 on the rotary table 45 when performing an inspection as described later.
【0011】以上説明したような構造の検査台20に前
述の制御棒クラスタ1を検査実施のために挿入した状態
を図6に示す。制御棒クラスタ1の実質的に外観検査を
要する部分は、支柱29の部分に位置し、外側から接近
可能となっている。同様に、シンブルプラグアセンブリ
5を検査台20に挿入セットした状態を図7に示してい
る。検査を要するシンブルプラグ6は、上方支柱27の
領域に位置し、外側から接近可能と成っている。以上の
説明から推測できるように、検査台20の中間胴33の
位置及び大きさは、実質的な検査作業を阻害しない程度
のものとする。FIG. 6 shows a state in which the above-described control rod cluster 1 is inserted into the inspection table 20 having the above-described structure for performing the inspection. The portion of the control rod cluster 1 which requires substantial visual inspection is located at the column 29 and is accessible from the outside. Similarly, FIG. 7 shows a state where the thimble plug assembly 5 is inserted and set on the inspection table 20. The thimble plug 6 that needs to be inspected is located in the region of the upper column 27 and is accessible from the outside. As can be inferred from the above description, the position and the size of the intermediate barrel 33 of the inspection table 20 are set to such a level as not to hinder a substantial inspection operation.
【0012】以上の検査台20を使用して内挿物の外観
検査を行う装置と方法を次に説明する。図8に示すよう
に、検査ピット50の放射線遮蔽水51の中に、回転テ
ーブル45が設けられ、これは、動力伝達機構47を介
してピット50のフロア上の回転駆動モータ49に連絡
している。そして、回転テーブル45の周りに支持架台
53が立設され、回転テーブル45の上に検査台20を
立てて置いたときにその模擬上部ノズル21を横方から
支持する。フロア上から張り出して設けられたフレーム
55の上に載設された昇降モータ57が、水中テレビカ
メラ59を昇降自在に支持している。そして、燃料集合
体取り扱いクレーン及び取扱工具を用いて、検査台20
を回転テーブル45の上に載せる。そして。制御棒クラ
スタ1を一点鎖線で図示するように検査台20に挿入
し、セットする。次に昇降用モータ57を駆動して、水
中テレビカメラ59をして制御棒クラスタ1の被検査部
である外面を走査せしめる。得られた外観撮像は、電気
信号に変えられ、図示しないモニタテレビの画面上に映
し出される。一側面の走査が完了すれば、所要角度例え
ば90°だけ回転テーブル45を回転し、制御棒クラス
タ1の隣接被検査側面を水中テレビカメラ59に対向さ
せ、前述の走査を繰り返す。勿論、回転テーブル45の
回転角は、非検査内挿物の計上に応じて適宜変更、調整
できるものであり、走査上下距離も変えられるものであ
る。An apparatus and method for inspecting the appearance of an inserted object using the inspection table 20 will be described below. As shown in FIG. 8, a rotary table 45 is provided in the radiation shielding water 51 of the inspection pit 50 and communicates with a rotary drive motor 49 on the floor of the pit 50 via a power transmission mechanism 47. I have. A support base 53 is erected around the rotary table 45, and supports the simulated upper nozzle 21 from the side when the inspection table 20 is placed upright on the rotary table 45. An elevating motor 57 mounted on a frame 55 extending from the floor supports an underwater television camera 59 so as to be able to move up and down. Then, using a crane and a tool for handling the fuel assembly, the inspection table 20 is used.
On the rotary table 45. And. The control rod cluster 1 is inserted and set in the inspection table 20 as shown by a dashed line. Next, the elevation motor 57 is driven to cause the underwater television camera 59 to scan the outer surface of the control rod cluster 1 which is the inspected portion. The obtained appearance image is converted into an electric signal and displayed on a monitor television screen (not shown). When the scanning of one side is completed, the rotary table 45 is rotated by a required angle, for example, 90 °, the side to be inspected of the control rod cluster 1 is opposed to the underwater television camera 59, and the above-described scanning is repeated. Of course, the rotation angle of the rotary table 45 can be appropriately changed and adjusted according to the count of non-inspection inserts, and the vertical scanning distance can also be changed.
【0013】[0013]
【発明の効果】以上説明したように、請求項1の本発明
によれば、燃料集合体内挿物が実際に使用される燃料集
合体を模擬した検査台に被検査内挿物を挿入、セットす
るので、短時間で安定し、所要の検査を効率よく行うこ
とができる。また、請求項2の発明によれば、前述のよ
うな検査台を回転テーブル上に載せて検査するので、検
査機器であるテレビカメラに対向する被検査外面を迅速
に切り替えることができ、内挿物の外観検査全体を短時
間で効率よく行うことができる。As described above, according to the first aspect of the present invention, the insert to be inspected is inserted and set on the inspection table simulating the fuel assembly in which the fuel assembly is actually used. Therefore, it is possible to stabilize in a short time and to efficiently perform a required inspection. According to the second aspect of the present invention, since the inspection table as described above is placed on the rotary table for the inspection, the external surface to be inspected facing the television camera as the inspection device can be quickly switched, and the interpolation can be performed. The whole appearance inspection of an object can be efficiently performed in a short time.
【図1】本発明の実施例を示す一部切欠き斜視図であ
る。FIG. 1 is a partially cutaway perspective view showing an embodiment of the present invention.
【図2】本発明の実施例を示す一部切欠き立断面図であ
る。FIG. 2 is a partially cut-away vertical sectional view showing an embodiment of the present invention.
【図3】前記実施例の上面図である。FIG. 3 is a top view of the embodiment.
【図4】図2のIV−IV線に沿った平断面図である。FIG. 4 is a plan sectional view taken along the line IV-IV in FIG. 2;
【図5】図2のV部を示す部分拡大側面図である。FIG. 5 is a partially enlarged side view showing a portion V in FIG. 2;
【図6】前記実施例の作用説明図である。FIG. 6 is an operation explanatory view of the embodiment.
【図7】前記実施例の作用説明図である。FIG. 7 is an operation explanatory view of the embodiment.
【図8】前記実施例の作用説明図である。FIG. 8 is an operation explanatory view of the embodiment.
【図9】本発明の検査対象の一を示す斜視図である。FIG. 9 is a perspective view showing one inspection object of the present invention.
【図10】本発明の検査対象の一を示す斜視図である。FIG. 10 is a perspective view showing one inspection object of the present invention.
【図11】本発明の検査対象の一を示す斜視図である。FIG. 11 is a perspective view showing one inspection object of the present invention.
【図12】従来技術の説明図である。FIG. 12 is an explanatory diagram of a conventional technique.
20 検査台 21 模擬上部ノズル 25 模擬下部ノズル 27 上方支柱 29 下方支柱 31 中間胴 33 案内管 45 回転テーブル Reference Signs List 20 inspection table 21 simulated upper nozzle 25 simulated lower nozzle 27 upper support 29 lower support 31 intermediate cylinder 33 guide tube 45 rotary table
───────────────────────────────────────────────────── フロントページの続き (58)調査した分野(Int.Cl.7,DB名) G21C 17/06 G21C 19/02 G21C 19/07 ──────────────────────────────────────────────────続 き Continued on the front page (58) Field surveyed (Int.Cl. 7 , DB name) G21C 17/06 G21C 19/02 G21C 19/07
Claims (2)
ノズルをそれぞれ模擬する模擬上部ノズル及び模擬下部
ノズル、前記両模擬ノズルを前記原子炉燃料集合体を模
擬して相互に連結する支柱、及び前記支柱の中間部に配
置され前記原子炉燃料集合体の制御棒案内管を模擬する
案内管を備えた中間胴からなることを特徴とする原子炉
燃料集合体内挿物の検査台。A simulated upper nozzle and a simulated lower nozzle that respectively simulate an upper nozzle and a lower nozzle of a reactor fuel assembly, a column connecting the simulated nozzles to each other by simulating the reactor fuel assembly, and An inspection table for an insert in a reactor fuel assembly, comprising an intermediate body provided with a guide tube simulating a control rod guide tube of the reactor fuel assembly, which is disposed at an intermediate portion of the column.
上に請求項1記載の検査台を載置し、原子炉燃料集合体
内挿物を該検査台の模擬上部ノズルに挿入保持し、前記
回転テーブルを回転しつつ該内挿物の外面をテレビカメ
ラで走査することを特徴とする原子炉燃料集合体内挿物
の検査方法。2. The inspection table according to claim 1 is mounted on a rotary table provided in radiation shielding water, and an insert in a reactor fuel assembly is inserted and held in a simulated upper nozzle of the inspection table. A method for inspecting an insert in a reactor fuel assembly, wherein an outer surface of the insert is scanned by a television camera while rotating a table.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP07143482A JP3137558B2 (en) | 1995-06-09 | 1995-06-09 | Inspection table and inspection method for inserts in reactor fuel assemblies |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP07143482A JP3137558B2 (en) | 1995-06-09 | 1995-06-09 | Inspection table and inspection method for inserts in reactor fuel assemblies |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPH08334592A JPH08334592A (en) | 1996-12-17 |
| JP3137558B2 true JP3137558B2 (en) | 2001-02-26 |
Family
ID=15339736
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP07143482A Expired - Lifetime JP3137558B2 (en) | 1995-06-09 | 1995-06-09 | Inspection table and inspection method for inserts in reactor fuel assemblies |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JP3137558B2 (en) |
Families Citing this family (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN115985531B (en) * | 2022-12-30 | 2026-04-24 | 中国船舶重工集团公司第七一九研究所 | Inspection stand for new fuel assemblies and control rod assemblies for marine nuclear power platforms |
-
1995
- 1995-06-09 JP JP07143482A patent/JP3137558B2/en not_active Expired - Lifetime
Also Published As
| Publication number | Publication date |
|---|---|
| JPH08334592A (en) | 1996-12-17 |
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