JPH03122593A - Tank type fast bredder reactor - Google Patents

Tank type fast bredder reactor

Info

Publication number
JPH03122593A
JPH03122593A JP1259979A JP25997989A JPH03122593A JP H03122593 A JPH03122593 A JP H03122593A JP 1259979 A JP1259979 A JP 1259979A JP 25997989 A JP25997989 A JP 25997989A JP H03122593 A JPH03122593 A JP H03122593A
Authority
JP
Japan
Prior art keywords
circulation pump
reactor
main circulation
coolant
reactor vessel
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
JP1259979A
Other languages
Japanese (ja)
Inventor
Shigeru Adachi
茂 足立
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 JP1259979A priority Critical patent/JPH03122593A/en
Publication of JPH03122593A publication Critical patent/JPH03122593A/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

  • Structures Of Non-Positive Displacement Pumps (AREA)

Abstract

PURPOSE:To enable treatment of a leak flow at a discharge side of a main circulation pump by providing an outer cylinder outside the main circulation pump and, at the same time, by providing a small hole in a vicinity of a suction side of the main circulation pump. CONSTITUTION:Surrounding a main circulation pump 3, piping joints 7 and in-core pipings 6, an outer cylinder 15 of which bottom end is fastened to a reactor core support structure 5, si provided. A to end of the outer cylinder 15 is connected to an outer barrel of an inetermediate heat exchanger 2 through seal bellows 16. In this case, a leak flow from a connection part of the main circulation pump 3 and the picking joints 7, flows out into the outer cylinder 15, however, as a coolant is sucked out from a small hole 17 provided at a suction side of the main circulation pump 3. no coolant flows out to an outside of the outer cylinder 15.

Description

【発明の詳細な説明】 [発明の目的] (産業上の利用分野) 本発明は特に原子炉容器内構造物を改良したタンク型高
速増殖炉に関する。
DETAILED DESCRIPTION OF THE INVENTION [Object of the Invention] (Industrial Application Field) The present invention particularly relates to a tank-type fast breeder reactor with improved reactor vessel internal structure.

(従来の技術) 第2図に示したように原子炉容器1内に設けた中間熱交
換器2と電磁ポンプを用いた主循環ポンプ3を合体させ
小型化、簡素化を指向したタンク型高速増殖炉が提案さ
れている。
(Prior art) As shown in Fig. 2, a tank-type high-speed pump is designed to reduce size and simplify the design by combining an intermediate heat exchanger 2 provided inside a reactor vessel 1 and a main circulation pump 3 using an electromagnetic pump. A breeder reactor has been proposed.

すなわち、原子炉容器1内には一次冷却材11が収容さ
れ、原子炉容器1の上部開口はループスラブ10により
閉鎖されている。原子炉容器1内には複数の燃料集合体
(図示せず)および制御棒(図示せず)等から構成され
る炉心4が設けられ、この炉心4は炉心支持構造物9に
支持されている。
That is, a primary coolant 11 is accommodated in the reactor vessel 1, and the upper opening of the reactor vessel 1 is closed by the loop slab 10. A reactor core 4 composed of a plurality of fuel assemblies (not shown), control rods (not shown), etc. is provided inside the reactor vessel 1, and this reactor core 4 is supported by a core support structure 9. .

またループスラブ10には一次冷却材と二次冷却材との
熱交換を行なう中間熱交換器2が支持されており、中間
熱交換器2の下部には電磁ポンプから構成される主循環
ポンプ3が合体され、その吐出側は配管継手7、炉内配
管6を介して炉心4に冷却材11を送り込めるようにし
ている。
Further, an intermediate heat exchanger 2 for exchanging heat between a primary coolant and a secondary coolant is supported on the loop slab 10, and a main circulation pump 3 composed of an electromagnetic pump is located below the intermediate heat exchanger 2. are combined, and the discharge side thereof allows coolant 11 to be sent into the reactor core 4 via a piping joint 7 and an in-furnace piping 6.

さらに、上部隔壁8と炉心支持構造物5とによって原子
炉容器1内の冷却材収容空間は上部プレナム12、下部
プレナム13および中間プレナム14とに区画されてい
る。
Furthermore, the coolant storage space within the reactor vessel 1 is divided into an upper plenum 12, a lower plenum 13, and an intermediate plenum 14 by the upper partition wall 8 and the core support structure 5.

(発明が解決しようとする課題) 第2図に提案されているタンク型高速増殖炉においては
、保守・補修の観点等から中間熱交換器2と合体された
主循環ポンプ3を炉外へ引抜く必要がある。そのため、
主循環ポンプ3の下部と配管継手7の接合部とは嵌め合
い構造とせざるを得ず、この部分が主循環ポンプ3の吐
出側で数kg/crlと高圧であることから1〜2%程
度(ポンプ流量費)のリークフローが存在する。このリ
ークフローは中間プレナム14の冷却材容積にとって無
視できず、定格時においては中間プレナム14内の冷却
材を約1時間以内にそっくり入れ替えてしまうほどの量
になる。このため、中間プレナム14内には中間熱交換
器で二次冷却材と熱交換され冷却された低温の冷却材で
満たされる。その結果として高温の冷却材が収容されて
いる上部プレナム12.との間を仕切る上部隔壁8の構
造健全性を損なうことになる。また、そのうえ上部プレ
ナム12と中間プレナム14の境界近傍の原子炉容器1
および炉心槽(炉心支持構造物の一部で炉心の側部に位
置するもの)に大きな軸方向温度分布を与え、これらの
構造健全性を損なう。さらに、中間プレナム14から上
部プレナム12へ流出する低温の冷却材によって流出部
の近傍に温度ゆらぎが発生し、該当部の構造健全性を損
なうなどの課題がある。
(Problems to be Solved by the Invention) In the tank type fast breeder reactor proposed in Fig. 2, the main circulation pump 3 combined with the intermediate heat exchanger 2 is pulled out of the reactor from the viewpoint of maintenance and repair. I need to take it out. Therefore,
The lower part of the main circulation pump 3 and the joint part of the piping joint 7 have to have a fitting structure, and since this part is under high pressure of several kg/crl on the discharge side of the main circulation pump 3, the pressure is about 1 to 2%. There is a leak flow of (pump flow rate). This leakage flow is not negligible for the coolant volume of the intermediate plenum 14, and is large enough to completely replace the coolant in the intermediate plenum 14 within about one hour at rated conditions. Therefore, the intermediate plenum 14 is filled with a low-temperature coolant that has been cooled by exchanging heat with the secondary coolant in the intermediate heat exchanger. Upper plenum 12, in which the resulting high temperature coolant is contained. This will damage the structural integrity of the upper partition wall 8 that partitions the space. In addition, the reactor vessel 1 near the boundary between the upper plenum 12 and the intermediate plenum 14
and the core barrel (a part of the core support structure located on the side of the core), resulting in a large axial temperature distribution, impairing their structural integrity. Furthermore, the low-temperature coolant flowing from the intermediate plenum 14 to the upper plenum 12 causes temperature fluctuations in the vicinity of the outflow section, which may impair the structural integrity of the corresponding section.

本発明は上記課題を解決するためになされたもので、主
循環ポンプ3と配管継手7の接合部からのリークフロー
を処理し、中間プレナム14内を流れのない状態(スタ
グナント)の冷却材とし、中間プレナム内に二次冷却材
の温度成層化を生せしめ、原子炉容器等の構造健全性を
はかったタンク型高速増殖炉を提供することにある。
The present invention was made in order to solve the above problems, and it treats the leak flow from the joint between the main circulation pump 3 and the pipe joint 7, and uses the coolant in a state where there is no flow (stagnant) in the intermediate plenum 14. An object of the present invention is to provide a tank-type fast breeder reactor in which temperature stratification of a secondary coolant is produced in an intermediate plenum to ensure structural integrity of a reactor vessel, etc.

[発明の構成] (課題を解決するための手段) 本発明は冷却材を収容し上部開口をループスラブで閉塞
された原子炉容器と、この原子炉容器内に設けられた前
記冷却材を該反応熱で加熱する炉心と、この炉心を支持
する炉心支持構造物と、前記ループスラブを貫通して設
けられ前記原子炉容器内の一次冷却材と該原子炉容器の
外部を循環する二次冷却材との熱交換を行なう中間交換
器と、この中間熱交換器の下部に設けられ冷却材を炉内
配管を介して前記炉心に送り込む主循環ポンプと、前記
原子炉容器の内部に設けられ該原子炉容器内の冷却材収
容空間を区画する隔壁とから構成されるタンク型高速増
殖炉において、前記主循環ポンプの外側に外筒を設ける
とともに前記主循環ポンプ吸込部近傍に小孔を設けたこ
とを特徴とする。
[Structure of the Invention] (Means for Solving the Problems) The present invention includes a reactor vessel that houses a coolant and has an upper opening closed with a loop slab, and a reactor vessel that houses a coolant and has an upper opening closed with a loop slab. A reactor core heated by reaction heat, a core support structure that supports the core, a primary coolant inside the reactor vessel that is provided through the loop slab, and a secondary cooling that circulates outside the reactor vessel. an intermediate exchanger that exchanges heat with the reactor; a main circulation pump that is installed at the bottom of the intermediate heat exchanger and that sends coolant into the reactor core through the reactor piping; and a main circulation pump that is installed inside the reactor vessel that In a tank-type fast breeder reactor consisting of a partition wall that partitions a coolant storage space in a reactor vessel, an outer cylinder is provided on the outside of the main circulation pump, and a small hole is provided near the suction part of the main circulation pump. It is characterized by

(作用) 主循環ポンプと配管継手部からリークする冷却材は外筒
の外側に流出しない。したがって、中間プレナム内の冷
却材はスタグナントな冷却材となり、中間プレナム内に
冷却材の温度成層化が生じる。
(Function) Coolant leaking from the main circulation pump and piping joints does not flow outside the outer cylinder. Therefore, the coolant in the intermediate plenum becomes a stagnant coolant, resulting in temperature stratification of the coolant within the intermediate plenum.

その結果、原子炉、炉心槽、上部隔壁の構造健全性上の
課題解決に有効である。また主循環ポンプと配管継手の
接合部からのリークフローは外筒内に流出するが、主循
環ポンプ吸込側に設けた小孔から冷却材が吸い込まれる
ため、外筒外へ冷却材の流出はなくなる。その結果、リ
ークフローがないため中間プレナムから上部プレナムへ
の冷却材の流出がなくなり温度ゆらぎを生じることはな
い。
As a result, it is effective in solving problems regarding the structural integrity of the reactor, core tank, and upper bulkhead. In addition, leakage flow from the joint between the main circulation pump and the piping joint flows into the outer cylinder, but since the coolant is sucked through the small hole provided on the main circulation pump suction side, the coolant does not flow out of the outer cylinder. It disappears. As a result, since there is no leakage flow, the coolant does not flow from the intermediate plenum to the upper plenum, and temperature fluctuations do not occur.

(実施例) 第1図を参照しながら本発明に係るタンク型高速増殖炉
の一実施例を説明する。
(Example) An example of a tank-type fast breeder reactor according to the present invention will be described with reference to FIG.

第1図において、原子炉容器1内には中間熱交換器2の
下方1.ニア生循環ポンプ3が配置され、炉心4の外側
に炉心支持構造物5に炉内配管6を介して支持されてい
る。炉内配管6には配管継手7が接続されている。炉心
4の上部から原子炉容器1の上部内壁面に沿って上部隔
壁8が設けられている。炉心4の上部からループスラブ
10を貫通して炉心上部機構9が設けられている。原子
炉容器1内には炉心4からの反応熱を冷却する冷却材1
1が収容され、炉心4を中心にして上方は上部プレナム
12を、下方は下部プレナム13を、中央部は中間プレ
ナム14をそれぞれ形成する。主循環ポンプ3、配管継
手7および炉内配管6を包囲して炉心支持構造物5に下
端が固定された外筒15が設けられている。この外筒1
5の上端はシールベローズ16を介して中間熱交換器2
の外胴に接続されている。外筒15上部壁面には多数の
小孔17が形成されており、この小孔17は主循環ポン
プ3の吸い込み側近傍に位置している。
In FIG. 1, inside the reactor vessel 1 there is a lower intermediate heat exchanger 2. A near live circulation pump 3 is disposed and is supported by a core support structure 5 via an in-core piping 6 outside the reactor core 4 . A piping joint 7 is connected to the furnace piping 6. An upper partition wall 8 is provided along the upper inner wall surface of the reactor vessel 1 from the upper part of the reactor core 4 . A core upper mechanism 9 is provided extending from the top of the core 4 through the loop slab 10 . Inside the reactor vessel 1 is a coolant 1 that cools the reaction heat from the reactor core 4.
1 is housed therein, and the upper part forms an upper plenum 12, the lower part forms a lower plenum 13, and the central part forms an intermediate plenum 14, respectively. An outer cylinder 15 whose lower end is fixed to the core support structure 5 is provided to surround the main circulation pump 3, the piping joint 7, and the in-reactor piping 6. This outer cylinder 1
The upper end of 5 is connected to the intermediate heat exchanger 2 via a seal bellows 16.
is connected to the outer body of the A large number of small holes 17 are formed in the upper wall surface of the outer cylinder 15, and these small holes 17 are located near the suction side of the main circulation pump 3.

しかして、上記実施例によれば主循環ポンプ3と配管継
手7の接合部からのリークフローは外筒15内に流出す
るが、主循環ポンプ3の吸い込み側に設けた小孔17か
ら冷却材が吸い込まれるため、外筒15の外側へ冷却材
の流出はなくなる。
According to the above embodiment, leakage flow from the joint between the main circulation pump 3 and the piping joint 7 flows into the outer cylinder 15, but the coolant flows through the small hole 17 provided on the suction side of the main circulation pump 3. Since the coolant is sucked in, the coolant does not flow out to the outside of the outer cylinder 15.

なお、第1図では炉心4を原子炉容器1の下部から支持
する構造の例で示したが、その他の支持方式、例えば炉
心を原子炉容器の側部から支持する構造の場合にも同様
の構造により主循環ポンプ吐出側のリークフローの処理
を行なうことができる。
Although FIG. 1 shows an example of a structure in which the reactor core 4 is supported from the bottom of the reactor vessel 1, the same method can be applied to other support methods, such as a structure in which the core is supported from the side of the reactor vessel. The structure allows leakage flow on the discharge side of the main circulation pump to be treated.

[発明の効果] 本発明によれば主循環ポンプ吐出側のリークフローを処
理することができ、中間プレナム内に冷却材の温度成層
化を生ぜしめ、原子炉容器、炉心槽、上部隔壁等の当該
部における構造健全性上の課題を解決することができる
[Effects of the Invention] According to the present invention, the leak flow on the discharge side of the main circulation pump can be treated, and temperature stratification of the coolant is created in the intermediate plenum, and damage to the reactor vessel, core tank, upper bulkhead, etc. Issues regarding the structural integrity of the relevant section can be resolved.

また外筒15内のり−クツロー回収の副産物として電磁
ポンプのコイルの冷却にも有効である。
It is also effective for cooling the coil of the electromagnetic pump as a by-product of collecting glue in the outer cylinder 15.

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

第1図は本発明に係るタンク型高速増殖炉の一実施例を
概略的に示す立面図、第2図はこの種タンク型高速増殖
炉として提案されている中間熱交換器と主循環ポンプを
合体させたタンク型高速増殖炉を概略的に示す立面図で
ある。 1・・・原子炉容器 2・・・中間熱交換器 3・・・主循環ポンプ 4・・・炉心 5・・・炉心支持構造物 6・・・炉内配管 7・・・・配管継手 8・・・上部隔壁 9・・・炉心上部機構 0・・・ループスラブ ト・・冷却材 2・・・上部プレナム 3・・・下部プレナム 4・・・中間プレナム 5・・・外筒 6・・・シールベローズ 7・・・小孔 (8733)代理人 弁理士 猪 股 祥 晃(ほか 
1名) 差 1 圓
Figure 1 is an elevational view schematically showing an embodiment of a tank-type fast breeder reactor according to the present invention, and Figure 2 is an intermediate heat exchanger and main circulation pump proposed for this type of tank-type fast breeder reactor. 1 is an elevational view schematically showing a tank-type fast breeder reactor in which the 1...Reactor vessel 2...Intermediate heat exchanger 3...Main circulation pump 4...Reactor core 5...Core support structure 6...In-reactor piping 7...Piping joint 8 ...Upper bulkhead 9...Upper core mechanism 0...Loop slab...Coolant 2...Upper plenum 3...Lower plenum 4...Intermediate plenum 5...Outer cylinder 6...Seal Bellows 7...Koko (8733) Agent Patent attorney Yoshiaki Inomata (and others)
1 person) Difference 1 circle

Claims (1)

【特許請求の範囲】[Claims] 冷却材を収容し上部開口をループスラブで閉鎖された原
子炉容器と、この原子炉容器内に設けられた前記冷却部
を核反応熱で加熱する炉心と、この炉心を支持する炉心
支持構造物と、前記ループスラブを貫通して設けられ前
記原子炉容器内の一次冷却材と該原子炉容器の外部を循
環する二次冷却材との熱交換を行なう中間熱交換器と、
この中間熱交換器の下部に設けられ冷却材を炉内配管を
介して前記炉心に送り込む主循環ポンプと、前記原子炉
容器の内部に設けられ該原子炉容器内の冷却材収容空間
を区画する隔壁とから構成されるタンク型高速増殖炉に
おいて、前記主循環ポンプの外側に外筒を設けるととも
に前記主循環ポンプ吸込部近傍に小孔を設けたことを特
徴とするタンク型高速増殖炉。
A reactor vessel that houses a coolant and has an upper opening closed with a loop slab, a reactor core that heats the cooling section provided in the reactor vessel with nuclear reaction heat, and a core support structure that supports this core. and an intermediate heat exchanger that is provided through the loop slab and performs heat exchange between the primary coolant inside the reactor vessel and the secondary coolant circulating outside the reactor vessel;
A main circulation pump is provided at the lower part of the intermediate heat exchanger and feeds coolant into the reactor core via the in-reactor piping, and a main circulation pump is provided inside the reactor vessel and partitions a coolant storage space within the reactor vessel. A tank type fast breeder reactor comprising a partition wall, characterized in that an outer cylinder is provided outside the main circulation pump, and a small hole is provided near the suction part of the main circulation pump.
JP1259979A 1989-10-06 1989-10-06 Tank type fast bredder reactor Pending JPH03122593A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP1259979A JPH03122593A (en) 1989-10-06 1989-10-06 Tank type fast bredder reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP1259979A JPH03122593A (en) 1989-10-06 1989-10-06 Tank type fast bredder reactor

Publications (1)

Publication Number Publication Date
JPH03122593A true JPH03122593A (en) 1991-05-24

Family

ID=17341592

Family Applications (1)

Application Number Title Priority Date Filing Date
JP1259979A Pending JPH03122593A (en) 1989-10-06 1989-10-06 Tank type fast bredder reactor

Country Status (1)

Country Link
JP (1) JPH03122593A (en)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2938691A1 (en) * 2008-11-19 2010-05-21 Commissariat Energie Atomique INTEGRATED TYPE SFR NUCLEAR REACTOR WITH IMPROVED COMPACITY AND CONVECTION
WO2010126028A1 (en) * 2009-04-27 2010-11-04 株式会社 東芝 Fast reactor

Cited By (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2938691A1 (en) * 2008-11-19 2010-05-21 Commissariat Energie Atomique INTEGRATED TYPE SFR NUCLEAR REACTOR WITH IMPROVED COMPACITY AND CONVECTION
WO2010057720A1 (en) * 2008-11-19 2010-05-27 Commissariat A L'energie Atomique Et Aux Energies Alternatives Sfr nuclear reactor of the integrated type with improved convection operation
WO2010126028A1 (en) * 2009-04-27 2010-11-04 株式会社 東芝 Fast reactor
US9093182B2 (en) 2009-04-27 2015-07-28 Kabushiki Kaisha Toshiba Fast reactor

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