JP2000111682A - Core internal structure of pressurized water reactor - Google Patents
Core internal structure of pressurized water reactorInfo
- Publication number
- JP2000111682A JP2000111682A JP10284429A JP28442998A JP2000111682A JP 2000111682 A JP2000111682 A JP 2000111682A JP 10284429 A JP10284429 A JP 10284429A JP 28442998 A JP28442998 A JP 28442998A JP 2000111682 A JP2000111682 A JP 2000111682A
- Authority
- JP
- Japan
- Prior art keywords
- baffle
- former
- fuel assembly
- core
- assembly loading
- 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.)
- Granted
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
- Cooling, Air Intake And Gas Exhaust, And Fuel Tank Arrangements In Propulsion Units (AREA)
Abstract
Description
【０００１】[0001]
【発明の属する技術分野】本発明は、加圧水型原子炉の
炉心構造に関する。The present invention relates to a core structure of a pressurized water reactor.
【０００２】[0002]
【従来の技術】加圧水型原子炉は、一般に、図２に示す
ような構造となっている。同図において、符号１は図示
しない蒸気発生器の一次冷却材出口ノズルに連通する入
口ノズル２と同じく蒸気発生器の一次冷却材入口ノズル
に連通する出口ノズル３とを有する原子炉容器であり、
この原子炉容器１内には炉心槽４が設けられている。2. Description of the Related Art A pressurized water reactor generally has a structure as shown in FIG. In the figure, reference numeral 1 denotes a reactor vessel having an inlet nozzle 2 communicating with a primary coolant outlet nozzle of a steam generator (not shown) and an outlet nozzle 3 communicating with a primary coolant inlet nozzle of the steam generator as well.
A reactor vessel 4 is provided in the reactor vessel 1.
【０００３】炉心槽４は円筒形状を成しており、この炉
心槽４の上端を閉塞する上部炉心支持板５には、炉心槽
４内に制御棒クラスタを導く複数本の制御棒クラスタ案
内管６が取り付けられている。また、炉心槽４は原子炉
容器１との間に環状のダウンカマー７を画成しており、
入口ノズル２から原子炉容器１内に流入した一次冷却水
はダウンカマー７内を下方に流れて炉心槽４の下端から
炉心槽４の内部に流入するようになっている。[0003] The core vessel 4 has a cylindrical shape, and a plurality of control rod cluster guide tubes for guiding the control rod clusters into the core vessel 4 are provided on an upper core support plate 5 closing the upper end of the core vessel 4. 6 is attached. The core vessel 4 defines an annular downcomer 7 between the reactor vessel 1 and the reactor vessel 1.
The primary cooling water flowing into the reactor vessel 1 from the inlet nozzle 2 flows downward in the downcomer 7 and flows into the core vessel 4 from the lower end of the core vessel 4.
【０００４】炉心槽４の内部には、下部炉心板８と上部
炉心板９が相対向して設けられている。これらの下部炉
心板８および上部炉心板９には多数の冷却水流通孔が形
成されており、上部炉心板９に形成された冷却水流通孔
から流出した一次冷却水は炉心槽４に形成された冷却水
出口管台１０を通って出口ノズル３に流入するようにな
っている。A lower core plate 8 and an upper core plate 9 are provided inside the core tank 4 so as to face each other. Many cooling water circulation holes are formed in the lower core plate 8 and the upper core plate 9, and primary cooling water flowing out of the cooling water circulation holes formed in the upper core plate 9 is formed in the core tank 4. The cooling water flows into the outlet nozzle 3 through the cooling water outlet nozzle 10.
【０００５】下部炉心板８と上部炉心板９との間には、
複数のバッフル板１２が設けられている。これらのバッ
フル板１２は炉心槽４の内側に図３に示すような燃料集
合体装荷領域１１を形成しており、この燃料集合体装荷
領域１１の内側角部１１ａと外側角部１１ｂはそれぞれ
二枚のバッフル板１２によって形成されている。[0005] Between the lower core plate 8 and the upper core plate 9,
A plurality of baffle plates 12 are provided. These baffle plates 12 form a fuel assembly loading region 11 as shown in FIG. 3 inside the core vessel 4, and the inner corner portion 11 a and the outer corner portion 11 b of the fuel assembly loading region 11 have two corners, respectively. It is formed by two baffle plates 12.
【０００６】また、バッフル板１２はステンレス鋼で形
成されており、炉心槽４とバッフル板１２との間に水平
に設けられたフォーマ板１３に図４に示す複数本のバッ
フルフォーマボルト１４によって固定されている。The baffle plate 12 is made of stainless steel, and is fixed to a former plate 13 horizontally provided between the core tank 4 and the baffle plate 12 by a plurality of baffle former bolts 14 shown in FIG. Have been.
【０００７】[0007]
【発明が解決しようとする課題】ところで、上記のよう
な構造の加圧水型原子炉では、炉心槽４内に流入した一
次冷却水が燃料集合体装荷領域１１に装荷された燃料集
合体によって高温に加熱されると、バッフル板１２やフ
ォーマ板１３が熱膨張することによって相対変位が生
じ、これによりバッフルフォーマボルト１４に応力が発
生する。この応力を低減するためにはバッフルフォーマ
ボルト１４を長くすることが有効であるが、バッフルフ
ォーマボルト１４を長くすると、バッフルフォーマボル
ト１４が燃料集合体装荷領域１１の内側角部１１ａ付近
で干渉し合うという問題が発生する。In the pressurized water reactor having the above structure, the primary cooling water flowing into the core vessel 4 is heated to a high temperature by the fuel assemblies loaded in the fuel assembly loading region 11. When heated, the baffle plate 12 and the former plate 13 are thermally expanded to cause relative displacement, thereby generating stress on the baffle former bolt 14. In order to reduce this stress, it is effective to lengthen the baffle former bolt 14. However, if the baffle former bolt 14 is elongated, the baffle former bolt 14 interferes near the inner corner 11a of the fuel assembly loading region 11. The problem of matching occurs.
【０００８】本発明は、上記の点に鑑みてなされたもの
で、燃料集合体装荷領域の内側角部付近でバッフルフォ
ーマボルトが干渉し合うことなくバッフルフォーマボル
トに発生する応力を低減することのできる加圧水型原子
炉の炉心構造を提供することを目的とするものである。SUMMARY OF THE INVENTION The present invention has been made in view of the above-described circumstances, and an object of the present invention is to reduce the stress generated in a baffle former bolt without interference of the baffle former bolts near the inner corner of the fuel assembly loading area. It is an object of the present invention to provide a pressurized water reactor core structure that can be used.
【０００９】[0009]
【課題を解決するための手段】上記の課題を解決するた
めに、本発明は、原子炉容器内に設けられた炉心槽と、
この炉心槽の内側に燃料集合体装荷領域を形成する複数
のバッフル板と、これらのバッフル板と前記炉心槽との
間に設けられたフォーマ板と、このフォーマ板に前記バ
ッフル板を固定する複数本のバッフルフォーマボルトと
を有する加圧水型原子炉の炉心構造において、前記燃料
集合体装荷領域の内側角部を形成する二枚のバッフル板
を互いに直角に溶接接合若しくは機械加工により削り出
して角バッフルとしたことを特徴とする。According to the present invention, there is provided a reactor vessel provided in a reactor vessel, comprising:
A plurality of baffle plates forming a fuel assembly loading region inside the core tank; a plurality of baffle plates provided between the baffle plates and the core tank; and a plurality of baffle plates fixing the baffle plate to the former plate. In a core structure of a pressurized water reactor having two baffle former bolts, two baffle plates forming inner corners of the fuel assembly loading region are cut out by welding or machining at right angles to each other to form a square baffle. It is characterized by having.
【００１０】[0010]
【発明の実施の形態】以下、図１を参照して本発明の一
実施形態について説明するが、図２乃至図４に示したも
のと同一部分には同一符号を付して説明する。図１は本
発明の一実施形態によって炉心槽４の内側に形成された
燃料集合体装荷領域１１の一部を示す平面図であり、同
図に示すように燃料集合体装荷領域１１の内側角部１１
ａはＬ形の角バッフル１５によって形成されている。こ
の角バッフル１５は二枚のバッフル板１２，１２を互い
に直角に溶接接合して構成され、バッフルフォーマボル
ト１４によってフォーマ板１３に固定されているDETAILED DESCRIPTION OF THE PREFERRED EMBODIMENTS One embodiment of the present invention will be described below with reference to FIG. 1. The same parts as those shown in FIGS. 2 to 4 are denoted by the same reference numerals. FIG. 1 is a plan view showing a part of a fuel assembly loading region 11 formed inside a core vessel 4 according to an embodiment of the present invention. As shown in FIG. Part 11
a is formed by an L-shaped square baffle 15. The square baffle 15 is formed by welding and joining two baffle plates 12, 12 at right angles to each other, and is fixed to the former plate 13 by baffle former bolts 14.
【００１１】上述した本発明の一実施形態では、燃料集
合体装荷領域１１の内側角部１１ａが二枚のバッフル板
１２，１２を互いに直角に溶接接合してなる角バッフル
１５で形成されているため、バッフルフォーマボルト１
４が燃料集合体装荷領域１１の内側角部１１ａ付近で干
渉し合うことがない。従って、バッフルフォーマボルト
１４の長さを従来よりも長くすることができ、これによ
りバッフルフォーマボルト１４に発生する応力を低減す
ることができる。In the embodiment of the present invention described above, the inner corner portion 11a of the fuel assembly loading region 11 is formed by a square baffle 15 formed by welding two baffle plates 12, 12 at right angles to each other. For baffle former bolt 1
4 does not interfere with each other near the inner corner 11a of the fuel assembly loading region 11. Therefore, the length of the baffle former bolt 14 can be made longer than that of the related art, so that the stress generated in the baffle former bolt 14 can be reduced.
【００１２】また、上述した実施形態ではバッフルフォ
ーマボルト１４の本数が従来よりも減少するため、コス
トの低減を図ることができる。さらに、上述した実施形
態では燃料集合体装荷領域１１の内側角部１１ａが二枚
のバッフル板１２，１２を互いに直角に溶接接合若しく
は機械加工により削り出して形成されているため、燃料
集合体装荷領域１１の内側角部１１ａに隙間が発生する
ことを防止でき、これにより燃料集合体装荷領域１１に
装荷された燃料集合体に対して悪影響を与える冷却水の
横流れの発生を防止できる。Further, in the above-described embodiment, the number of baffle former bolts 14 is reduced as compared with the conventional case, so that the cost can be reduced. Further, in the above-described embodiment, the inner corner portion 11a of the fuel assembly loading region 11 is formed by welding the two baffle plates 12, 12 at right angles to each other by welding or machining, so that the fuel assembly loading is performed. A gap can be prevented from being generated at the inner corner portion 11a of the region 11, thereby preventing a lateral flow of the cooling water that adversely affects the fuel assemblies loaded in the fuel assembly loading region 11.
【００１３】[0013]
【発明の効果】以上説明したように、本発明によれば、
燃料集合体装荷領域の内側角部付近でバッフルフォーマ
ボルトが干渉し合うことなくバッフルフォーマボルトに
発生する応力を低減することのできる加圧水型原子炉の
炉心構造を提供できる。As described above, according to the present invention,
It is possible to provide a core structure of a pressurized water reactor that can reduce stress generated in a baffle former bolt without interference of the baffle former bolt near an inner corner portion of a fuel assembly loading region.
【図１】本発明の一実施形態によって炉心槽の内側に形
成された燃料集合体装荷領域の一部を示す平面図であ
る。FIG. 1 is a plan view showing a part of a fuel assembly loading region formed inside a core tank according to an embodiment of the present invention.
【図２】加圧水型原子炉の縦断面図である。FIG. 2 is a longitudinal sectional view of a pressurized water reactor.
【図３】従来の加圧水型原子炉の炉心構造によって炉心
槽の内側に形成された燃料集合体装荷領域の一部を示す
平面図である。FIG. 3 is a plan view showing a part of a fuel assembly loading region formed inside a core tank by a core structure of a conventional pressurized water reactor.
【図４】図３のＡ−Ａ線に沿う断面図である。FIG. 4 is a sectional view taken along line AA of FIG. 3;
１ 原子炉容器 ４ 炉心槽 ８ 下部炉心板 ９ 上部炉心
板 １１ 燃料集合体装荷領域 １１ａ 内側角
部 １２ バッフル板 １３ フォー
マ板 １４ バッフルフォーマボルト １５ 角バッ
フルDESCRIPTION OF SYMBOLS 1 Reactor vessel 4 Core tank 8 Lower core plate 9 Upper core plate 11 Loading area of fuel assembly 11a Inner corner 12 Baffle plate 13 Former plate 14 Baffle former bolt 15 Square baffle
Claims (1)
の炉心槽の内側に燃料集合体装荷領域を形成する複数の
バッフル板と、これらのバッフル板と前記炉心槽との間
に設けられたフォーマ板と、このフォーマ板に前記バッ
フル板を固定する複数本のバッフルフォーマボルトとを
有する加圧水型原子炉の炉心構造において、 前記燃料集合体装荷領域の内側角部を形成する二枚のバ
ッフル板を互いに直角に溶接接合若しくは機械加工によ
り削り出して角バッフルとしたことを特徴とする加圧水
型原子炉の炉心構造。1. A core tank provided in a nuclear reactor vessel, a plurality of baffle plates forming a fuel assembly loading area inside the core tank, and a plurality of baffle plates provided between the baffle plates and the core tank. In a core structure of a pressurized water reactor having a formed former plate and a plurality of baffle former bolts for fixing the baffle plate to the former plate, two sheets forming inner corners of the fuel assembly loading region are provided. A core structure for a pressurized water reactor, wherein baffle plates are cut at right angles to each other by welding or machining to form square baffles.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP28442998A JP4301604B2 (en) | 1998-10-06 | 1998-10-06 | Pressurized water reactor |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP28442998A JP4301604B2 (en) | 1998-10-06 | 1998-10-06 | Pressurized water reactor |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JP2000111682A true JP2000111682A (en) | 2000-04-21 |
| JP4301604B2 JP4301604B2 (en) | 2009-07-22 |
Family
ID=17678446
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP28442998A Expired - Lifetime JP4301604B2 (en) | 1998-10-06 | 1998-10-06 | Pressurized water reactor |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JP4301604B2 (en) |
Cited By (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| KR101102105B1 (en) | 2010-06-16 | 2012-01-18 | 두산중공업 주식회사 | Baffle coupling device of reactor superstructure |
| US8130895B2 (en) * | 2003-10-01 | 2012-03-06 | Areva Np | Method and a device for packaging leaky nuclear fuel rods for the purposes of transport and long-duration storage or warehousing |
| JP2012512417A (en) * | 2008-12-17 | 2012-05-31 | ウエスチングハウス・エレクトリック・カンパニー・エルエルシー | Core shroud corner connections |
| JP2022087587A (en) * | 2020-12-01 | 2022-06-13 | 三菱重工業株式会社 | Analytical equipment, analysis method and program |
-
1998
- 1998-10-06 JP JP28442998A patent/JP4301604B2/en not_active Expired - Lifetime
Cited By (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US8130895B2 (en) * | 2003-10-01 | 2012-03-06 | Areva Np | Method and a device for packaging leaky nuclear fuel rods for the purposes of transport and long-duration storage or warehousing |
| JP2012512417A (en) * | 2008-12-17 | 2012-05-31 | ウエスチングハウス・エレクトリック・カンパニー・エルエルシー | Core shroud corner connections |
| KR101574826B1 (en) * | 2008-12-17 | 2015-12-04 | 웨스팅하우스 일렉트릭 컴퍼니 엘엘씨 | Nuclear reactor core shroud with corner members |
| KR101102105B1 (en) | 2010-06-16 | 2012-01-18 | 두산중공업 주식회사 | Baffle coupling device of reactor superstructure |
| JP2022087587A (en) * | 2020-12-01 | 2022-06-13 | 三菱重工業株式会社 | Analytical equipment, analysis method and program |
| JP7493436B2 (en) | 2020-12-01 | 2024-05-31 | 三菱重工業株式会社 | Analysis device, analysis method, and program |
Also Published As
| Publication number | Publication date |
|---|---|
| JP4301604B2 (en) | 2009-07-22 |
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