JPS60179687A - Fuel aggregate - Google Patents

Fuel aggregate

Info

Publication number
JPS60179687A
JPS60179687A JP59035168A JP3516884A JPS60179687A JP S60179687 A JPS60179687 A JP S60179687A JP 59035168 A JP59035168 A JP 59035168A JP 3516884 A JP3516884 A JP 3516884A JP S60179687 A JPS60179687 A JP S60179687A
Authority
JP
Japan
Prior art keywords
coolant
fuel
fuel assembly
capture device
radioactive corrosion
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
JP59035168A
Other languages
Japanese (ja)
Inventor
原 世悦
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.)
Toshiba Corp
Original Assignee
Toshiba Corp
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 Toshiba Corp filed Critical Toshiba Corp
Priority to JP59035168A priority Critical patent/JPS60179687A/en
Publication of JPS60179687A publication Critical patent/JPS60179687A/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

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  • Inert Electrodes (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】 〔発明の技術分野〕 本発明は、高速増殖炉に使用される燃料果合体に関する
DETAILED DESCRIPTION OF THE INVENTION [Technical Field of the Invention] The present invention relates to a fuel assembly used in a fast breeder reactor.

〔従来技術と・七の問題点〕[7 problems with conventional technology]

高速増殖炉においては、冷却材としC1一般に液体ナト
リウムで代表さaるアルカリ土類金属が用いらF’LC
いる。そしC1このような液体金属冷却材は、原子炉容
器内の炉心で加熱された後、容器外に設けられた1次冷
却系へと導ひかれ、再び原子炉容器内へと戻され、循環
する。
In fast breeder reactors, alkaline earth metals such as C1 and liquid sodium are generally used as coolants, F'LC
There is. After C1, such liquid metal coolant is heated in the reactor core inside the reactor vessel, it is guided to the primary cooling system installed outside the vessel, and then returned to the reactor vessel and circulated. .

ところで、高速増殖炉の場合、核燃料要素の被覆管や炉
心構造物は、通常、ステン°−レス鋼で構成されるが、
これ等の構成材料が中性子の照射音うけると、上記構成
材料に含まれCいる鉄、コバルト等が核反応?起し、マ
ンガン−54,コバルト−60,コバルト−58等の放
射性核種が多数に生成される。この構成材料は冷却材と
しC用いられている前述のアルカリ土類金jiAVこよ
り腐食され冷却材中へ放出さaる。このとき前述の放射
性核4粛も冷却材中へ放出され、いわゆる放射性14食
生成物が冷却材へ混入することになる。
By the way, in the case of fast breeder reactors, the cladding tubes and core structures of the nuclear fuel elements are usually made of stainless steel.
When these constituent materials receive the sound of neutron irradiation, the iron, cobalt, etc. contained in the above constituent materials undergo a nuclear reaction? and a large number of radionuclides such as manganese-54, cobalt-60, and cobalt-58 are produced. This constituent material is corroded by the above-mentioned alkaline earth gold used as a coolant and released into the coolant. At this time, the aforementioned radioactive nuclei are also released into the coolant, and so-called radioactive 14 edible products are mixed into the coolant.

冷却材へ混入した放射性腐食生成物は冷却材の流れに従
っC,1次冷却系へと運ばれ、中間熱交換器等の1次冷
却系機器配管の壁面等に沈着する。
The radioactive corrosion products mixed into the coolant are carried to the primary cooling system according to the flow of the coolant, and are deposited on the walls of the pipes of primary cooling system equipment such as intermediate heat exchangers.

このように、1次冷却系の壁面等に沈着した放射性腐食
生成物の放射能はボング、熱交換器、パルブ、流量計等
の機器やこれ等の機器に接続された配管の保守、補修等
の作業に障害金与える。特に、マンガン−54,コバル
)’ −60、コバルト−58等の生成敬も多く、半減
期も長いためVこその影響が大きい。
In this way, the radioactivity of radioactive corrosion products deposited on the walls of the primary cooling system can be removed by maintenance and repair of equipment such as bongs, heat exchangers, valves, flow meters, etc., and the piping connected to these equipment. Give disability money for work. In particular, manganese-54, cobalt-58, cobalt-58, etc. are often produced and have a long half-life, so V has a large influence.

そこで、このような不具合を解消するために、最近では
、ニッケルが高温の液体金属ナトリウム中でマンガン−
54,コバル)’−60’4の放射性核種全効率よく捕
獲する性質を有しCいること全利用した放射性腐食生成
物捕獲装置を原子炉容器内に設置−することが考えられ
Cいる。この放射性腐食生成物捕獲装置は、炉心の冷却
材用1コに対向させご1つまり炉心上方に前記ニッケル
等の捕獲材を収容した要素を複数配置し、炉心から流出
した冷却材全上記捕獲材しこ直接接触させることによっ
て、放射性核種全捕獲するよう((している。
Therefore, in order to solve this problem, recently, nickel has been replaced with manganese in high-temperature liquid metal sodium.
It is considered to install a radioactive corrosion product capture device that utilizes all of the radionuclides of 54, 60 and 4 with high efficiency in the reactor vessel. This radioactive corrosion product capture device has a plurality of elements containing the capture material such as nickel placed above the reactor core, facing one core coolant, and collects all of the coolant flowing out from the core. All radionuclides are captured by direct contact.

前記のような捕獲装置にあっCは、設置する場合Vこ炉
心の上方に空間が必要となる。その空間は効率よく放射
性腐食生成物を捕獲するには約30crnといわれてい
る。したがって、上記捕獲装置全設置するには原子炉容
器を大型化する必要があるという問題がある。
When installing a capture device such as the one described above, a space is required above the reactor core. The space is said to be about 30 crn to efficiently capture radioactive corrosion products. Therefore, there is a problem in that the reactor vessel needs to be enlarged in order to install all of the above-mentioned capture devices.

そこで、上記のような問題ケ避けるために、多数配置さ
れ、冷却材の主流路全形成する燃料集合体の燃料要素上
部の空間に捕獲装置を設置することが考えらt″LCい
る。しかし、この場合には燃料集合体間の間隙?流れる
冷却材により燃料集合体のラッパ管外周面が1jイ食し
C冷ムD材中に放出された放射性腐食生成物の捕獲がで
きないという問題がある。
Therefore, in order to avoid the above-mentioned problems, it is considered that a large number of capture devices are installed in the space above the fuel elements of the fuel assembly that form all the main channels of the coolant.However, In this case, there is a problem that the outer circumferential surface of the wrapper tube of the fuel assembly is corroded by the coolant flowing through the gap between the fuel assemblies, making it impossible to capture the radioactive corrosion products released into the cold material C.

〔発明の目的〕[Purpose of the invention]

本発明は、このような事情に鑑みCなされたもので、ピ
の目的とするところは、燃料集合体内の燃料要素上部の
空間に放射性腐食生成物捕獲装置を設置しながら、燃料
集合体間の間隙を流れる冷却材中に含までとる放射性1
g食生成物をも捕獲できる燃料集合体ケ提供することに
ある。
The present invention has been developed in view of the above circumstances, and its primary purpose is to install a radioactive corrosion product capture device in the space above the fuel elements within the fuel assembly, while at the same time Radioactivity contained in the coolant flowing through the gap1
An object of the present invention is to provide a fuel assembly that can also capture edible products.

〔発明の概要〕[Summary of the invention]

本発明は、横断面形状が正六角形のラッパ管およびハン
ドリングヘッド、エントランスノズル。
The present invention relates to a trumpet tube, a handling head, and an entrance nozzle each having a regular hexagonal cross-sectional shape.

燃料要素、燃料要素支持機構と燃料要素上部に配置した
放射性腐食生成物捕獲装置から成る燃料集合体+cおい
て、放射性腐食生成物捕獲装置下部のラッパ管部Vこ燃
料集合体間の間隙ケ流れる冷却材を燃料乗合体内部に導
入するための冷却材導入孔を設けるとともに、ノ・ンド
リングヘノド外周面Vこ燃料集合体間の間隙全局部的V
こ小さくするためのつば金設けた燃料集合体である。
In a fuel assembly +c consisting of a fuel element, a fuel element support mechanism, and a radioactive corrosion product capture device disposed above the fuel element, the gap between the fuel assemblies flows through the trumpet pipe section V at the bottom of the radioactive corrosion product capture device. A coolant introduction hole is provided for introducing the coolant into the fuel assembly, and the gap between the fuel assemblies is locally
This is a fuel assembly with a collar to make it smaller.

〔発明の効果〕〔Effect of the invention〕

高速増殖炉にづいC1原子炉容器下部よ’) iAt人
した冷却材の多くは燃料集合体のエントランスノズルに
設けられCいるオリスイス孔より燃料乗合体内部に流入
し、ラッパ管Vこより外側全拘束された燃料要素部を通
流しC燃料集合体の頂部を形成しCいるノ・ンドリング
ヘソド部から炉心上方へυ1を出する。一方、オリフィ
ス孔より燃料集合体内Vこ流入しなかった冷却材は、多
数配置さくLCいる燃料集合体の間の間隙を流れ炉心上
方へ流出する。
In a fast breeder reactor, most of the coolant flowing into the lower part of the C1 reactor vessel flows into the fuel assembly through the orifice hole C provided in the entrance nozzle of the fuel assembly, and from the trumpet tube V the entire outside is restrained. υ1 is passed through the heated fuel element part to form the top of the C fuel assembly, and is ejected from the no-end ring head section above the core. On the other hand, the coolant that has not flown into the fuel assembly through the orifice holes flows through the gaps between the fuel assemblies arranged in large numbers and flows out to the upper part of the reactor core.

しかし、本発明の構成であると、燃料集合体間の間隙k
Kれハンドリングヘッド部に達した冷却材はハンドリン
グヘッド外周面しこ設けられたつばにより流路が局部的
Qこ小さくなっCいるため炉心上方への流出が妨げられ
、ラッパ管部Vこ設けられた冷却材導入孔より燃料集合
体内Vこ流入する。この流入した冷却材は、エントラン
スノズルのオリフィス孔より流入した冷却材と一′gr
iに燃料要素上部の放射性腐食生成物捕獲装置部を通流
し、その結果放射性腐食生成物が除去さ7″Lだ冷却材
がノ・ンドリングヘノド部から炉心上方へ流出する。し
たがっC1原子炉谷器から1次冷却系へ流出する冷却材
は放射性腐食生成物が除去された冷却材であり、放射性
腐食生成物の1次冷却系への沈着全防止できる。
However, with the configuration of the present invention, the gap k between the fuel assemblies
The flow path of the coolant that has reached the handling head becomes locally small due to the collar provided on the outer circumferential surface of the handling head, preventing it from flowing upward into the reactor core. The coolant flows into the fuel assembly through the coolant introduction hole. This inflowing coolant is equal to the coolant inflowing from the orifice hole of the entrance nozzle.
As a result, the radioactive corrosion products are removed and the coolant flows upward through the reactor core from the nozzle nodule.Therefore, the C1 reactor valley The coolant flowing out to the primary cooling system is a coolant from which radioactive corrosion products have been removed, and deposition of radioactive corrosion products into the primary cooling system can be completely prevented.

本発明では、燃料集合体間Vこ設置しl乞放射性腐食生
成物捕獲装置だけで燃料集合体間の間隙分流する冷却材
中に含まれる放射性1食生成物金も捕獲できるため、燃
料集合体外周面に放射性腐食生成物捕獲装置全設置する
必要がなく、また燃料集合体自体全大型化する必要もl
+/−まため、原子炉プラントの高価格化防止にd与で
きる。
In the present invention, the radioactive corrosion product gold contained in the coolant flowing through the gap between the fuel assemblies can also be captured with just the radioactive corrosion product capture device installed between the fuel assemblies. There is no need to install a radioactive corrosion product capture device on the surrounding surface, and there is no need to increase the size of the fuel assembly itself.
+/- In addition, it can help prevent the price increase of nuclear reactor plants.

〔発明の実施例〕[Embodiments of the invention]

第1図は本発明の一実施例に係る燃料集合体の概略構造
を示す斜視図であり、第2図はこの燃料集合体上部の概
略構造を示す縦断面図である。この燃料集合体は、ハン
ドリングヘッド1と、燃料要素2と図示しない燃料要素
支持機構、そしCそれらの外側拘束等の機能をもつ横断
面が正六角形のラッパ管3と、冷却材を燃料集合体内に
導入する機能金もつエントランスノズル4と、燃料要素
2の上部の空間に設置されたニッケル製の金網から成る
放射性腐食生成物捕獲装置5から構成さaCいる。上記
ラッパ管には燃料集合体間の間隙全維持するためのスペ
ーサーパッド6がその外周面に取付けられCおり、エン
トランスノズル4には冷却材全上記燃料集合体内に導入
するためにオリフィス孔7が設けられている。また、ハ
ンドリングヘッド1の外周面には、燃料集合体を炉心に
設置した場合に隣接する燃料集合体との間隙が1mm以
゛Fになるようなつげ8を全周に取付けてるる。
FIG. 1 is a perspective view showing a schematic structure of a fuel assembly according to an embodiment of the present invention, and FIG. 2 is a vertical sectional view showing a schematic structure of an upper part of this fuel assembly. This fuel assembly includes a handling head 1, a fuel element 2, a fuel element support mechanism (not shown), a trumpet tube 3 with a regular hexagonal cross section that functions to restrain the outside of these components, and a coolant inside the fuel assembly. The radioactive corrosion product trapping device 5 consists of an entrance nozzle 4 with a functional metal introduced into the fuel element 2, and a radioactive corrosion product capture device 5 made of a nickel wire mesh installed in the space above the fuel element 2. A spacer pad 6 is attached to the outer peripheral surface of the wrapper tube to maintain the entire gap between the fuel assemblies, and an orifice hole 7 is provided in the entrance nozzle 4 to introduce all the coolant into the fuel assemblies. It is provided. Further, on the outer circumferential surface of the handling head 1, barbs 8 are attached around the entire circumference so that when the fuel assemblies are installed in the reactor core, the gap between adjacent fuel assemblies is 1 mm or more.

さらに、燃料要素2と放射性腐食生成物捕獲装置5の空
間部のラッパ管壁には燃料集合体内に冷却材を導入する
だめの円形の冷却材導入孔9が各面に2個設けCいる。
Furthermore, two circular coolant introduction holes 9 are provided on each surface of the wrapper tube wall in the space between the fuel element 2 and the radioactive corrosion product capture device 5 for introducing the coolant into the fuel assembly.

この燃料集合体が炉心に多数配置さnた状態では、エン
トランスノズル4のオリフィス孔7より燃料集合体内へ
流入しなかった冷却材りは燃料集合体間の間隙を流れる
。このとさ、放射化されたラッパ管外周面が腐食しC冷
却材り中に放射性腐食生成物が混入する。そしC1この
冷却材りがハンドリングヘッド1部を通過しC炉心上方
へ流出しようとするとき、ハンドリングヘッド1の外周
面に取付けらa〔いるつば8のためして流路が極単に狭
められCいるため抵抗が大きくなる。Uの結果、冷却材
りは放射性腐食生成物捕獲装置5のF部のラッパ管壁に
設けられた冷却材導入孔9より燃料部合体内に流入する
。この冷却材導入孔より流入した冷却材は、エントラン
スノズル4のオリフィス孔7より燃料集合体内しζ流入
した冷却材と一諸に放射性腐食生成物捕獲装置?L s
 *通流し、ハンドリングヘッド1より炉心上方へ流出
する。冷却材中によまれる放射性腐食生成物は放射性腐
食生成物捕獲装置5を通流するとき捕獲され、Ai1述
した効果が得られる。
When a large number of fuel assemblies are arranged in the reactor core, the coolant that does not flow into the fuel assemblies through the orifice hole 7 of the entrance nozzle 4 flows through the gaps between the fuel assemblies. At this time, the outer peripheral surface of the activated trumpet tube corrodes, and radioactive corrosion products mix into the C coolant. When this coolant passes through the handling head 1 and is about to flow out into the upper part of the reactor core, the flow path is extremely narrowed due to the collar 8 attached to the outer peripheral surface of the handling head 1. resistance increases. As a result of U, the coolant flows into the fuel assembly through the coolant introduction hole 9 provided in the wrapper tube wall of the F section of the radioactive corrosion product capture device 5. The coolant flowing in through this coolant introduction hole is combined with the coolant flowing into the fuel assembly through the orifice hole 7 of the entrance nozzle 4 into a radioactive corrosion product capture device. Ls
*It flows through and flows out from the handling head 1 to the upper part of the reactor core. The radioactive corrosion products drawn into the coolant are captured when flowing through the radioactive corrosion product capture device 5, and the effect described in Ai1 is obtained.

〔発明の他の実施例〕[Other embodiments of the invention]

本発明は上述した実施例に限定さてしるものではない。 The present invention is not limited to the embodiments described above.

実施例では冷却材導入孔の形状を円形としたが長方形等
の他の形状でろりCもよい。また、その数も各面に2個
と限定されるものではない。
In the embodiment, the shape of the coolant introduction hole was circular, but other shapes such as a rectangle may also be used. Further, the number is not limited to two on each surface.

放射性腐食生成物捕獲装置にはニッケル製の金711岩
を用いCいるが、ワイヤや板から成る捕獲装置醒でもよ
く、また材質もニッケル合金もしくはニッケルメッキの
施されたステンレス鋼でもよい。
Although gold 711 rock made of nickel is used for the radioactive corrosion product capture device, the capture device may be made of wire or plate, and the material may be nickel alloy or nickel-plated stainless steel.

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

第1図は本発明の一実施例(・こ係る燃料集合体の概略
構造を示す斜視図であり、第2図は一部省略縦断面図で
ある。 l・・・ハンドリングヘッド、2・・・燃料要素。 3・・・ラッパ管、 4・・・エントランスノズル。 5・・・放射性腐食生成物捕獲装置。 6・・・スペーサーパッド、 7・・・オリフィス孔。 8・・・つば、 9・・冷却材導入孔。 L・・・冷却材。 代理人 弁理士 則 近 憑 佑 (ほか1名) 第 1 図 第 2 図
FIG. 1 is a perspective view showing a schematic structure of a fuel assembly according to an embodiment of the present invention, and FIG. 2 is a partially omitted longitudinal sectional view. 1... Handling head, 2...・Fuel element. 3...Trumpet pipe, 4...Entrance nozzle. 5...Radioactive corrosion product capture device. 6...Spacer pad, 7...Orifice hole. 8...Brim, 9 ...Coolant introduction hole. L...Coolant. Agent: Patent attorney Noriyuki Chika (and one other person) Figure 1 Figure 2

Claims (1)

【特許請求の範囲】 横断面形状が正六角形のラッパ管およびハンドリングヘ
ッド、エントランスノズル、燃料要素。 燃料要素支持機構と前記燃料要素上部に配置した放射性
腐食生成物捕獲装置から成る燃料集合体げおいて、前記
ハンドリングヘッド外周面に燃料−束合体間の間隙合手
さくするためのつばを、前記放射性核種捕獲装置下部の
ラッパ管部に燃料集合体内に冷却材を導入するだめの冷
却材導入孔を、それぞれ具備しCなることを特徴とする
燃料集合体。
[Claims] A trumpet tube having a regular hexagonal cross-sectional shape, a handling head, an entrance nozzle, and a fuel element. A fuel assembly consisting of a fuel element support mechanism and a radioactive corrosion product capture device disposed on the upper part of the fuel element is provided, and a collar is provided on the outer peripheral surface of the handling head to close the gap between the fuel bundle assembly. A fuel assembly characterized in that each of the trumpet tubes at the bottom of the radionuclide capture device is provided with coolant introduction holes for introducing coolant into the fuel assembly.
JP59035168A 1984-02-28 1984-02-28 Fuel aggregate Pending JPS60179687A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP59035168A JPS60179687A (en) 1984-02-28 1984-02-28 Fuel aggregate

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP59035168A JPS60179687A (en) 1984-02-28 1984-02-28 Fuel aggregate

Publications (1)

Publication Number Publication Date
JPS60179687A true JPS60179687A (en) 1985-09-13

Family

ID=12434335

Family Applications (1)

Application Number Title Priority Date Filing Date
JP59035168A Pending JPS60179687A (en) 1984-02-28 1984-02-28 Fuel aggregate

Country Status (1)

Country Link
JP (1) JPS60179687A (en)

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
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
JP2009058505A (en) * 2007-08-31 2009-03-19 Global Nuclear Fuel Americas Llc Debris shield for upper tie plate in nuclear fuel bundle and method for filtering 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
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
JP2009058505A (en) * 2007-08-31 2009-03-19 Global Nuclear Fuel Americas Llc Debris shield for upper tie plate in nuclear fuel bundle and method for filtering 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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