JP4301604B2 - Pressurized water reactor - Google Patents

Pressurized water reactor Download PDF

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Publication number
JP4301604B2
JP4301604B2 JP28442998A JP28442998A JP4301604B2 JP 4301604 B2 JP4301604 B2 JP 4301604B2 JP 28442998 A JP28442998 A JP 28442998A JP 28442998 A JP28442998 A JP 28442998A JP 4301604 B2 JP4301604 B2 JP 4301604B2
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Prior art keywords
baffle
reactor
former
plate
core
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JP28442998A
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Japanese (ja)
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JP2000111682A (en
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浩和 庄村
力 栗村
和宏 後藤
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Mitsubishi Heavy Industries Ltd
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Mitsubishi Heavy Industries Ltd
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    • 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

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  • Cooling, Air Intake And Gas Exhaust, And Fuel Tank Arrangements In Propulsion Units (AREA)

Description

【０００１】
【発明の属する技術分野】
本発明は、加圧水型原子炉に関する。
【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。
【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。
【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。
【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。
【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。
【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。
【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を提供することを目的とするものである。
【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炉心構造の加圧水型原子炉において、前記燃料集合体装荷領域の内側角部を、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形成したＬ形の角バッフルとし、上記内側角部付近で上記バッフルフォーマボルトが干渉し合うことのないようにして固定したことを特徴とする。
【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１１ａ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若しくは機械加工により削り出して形成され、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。
【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若しくは機械加工により削り出して形成したＬ形の角バッフル１５としているため、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。
【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。
【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ができ、また、バッフルフォーマボルト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加圧水型原子炉を提供できる。
【図面の簡単な説明】
【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。
【図２】加圧水型原子炉の縦断面図である。
【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。
【図４】図３のＡ−Ａ線に沿う断面図である。
【符号の説明】
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[0001]
BACKGROUND OF THE INVENTION
The present invention relates to a pressurized water reactor.
[0002]
[Prior art]
A pressurized water reactor generally has a structure as shown in FIG. In the figure, reference numeral 1 denotes a nuclear 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, A reactor core 4 is provided in the reactor vessel 1.
[0003]
The reactor core 4 has a cylindrical shape, and a plurality of control rod cluster guide tubes 6 for guiding control rod clusters into the reactor core 4 are attached to an upper core support plate 5 that closes the upper end of the reactor core 4. It has been. Further, the reactor core tank 4 defines an annular downcomer 7 between itself and the reactor vessel 1, and the primary cooling water flowing into the reactor vessel 1 from the inlet nozzle 2 flows downward in the downcomer 7. Then, it flows into the core tank 4 from the lower end of the core tank 4.
[0004]
In the core tank 4, a lower core plate 8 and an upper core plate 9 are provided to face each other. The lower core plate 8 and the upper core plate 9 are formed with a large number of cooling water flow holes, and the primary cooling water flowing out from the cooling water flow holes formed in the upper core plate 9 is formed in the core tank 4. The cooling water outlet nozzle 10 flows into the outlet nozzle 3.
[0005]
A plurality of baffle plates 12 are provided between the lower core plate 8 and the upper core plate 9. These baffle plates 12 form a fuel assembly loading region 11 as shown in FIG. 3 inside the reactor core 4, and each of the inner corner portion 11 a and the outer corner portion 11 b of the fuel assembly loading region 11 has two. It is formed by a single baffle plate 12.
[0006]
The baffle plate 12 is made of stainless steel, and is fixed to a former plate 13 provided horizontally between the reactor core 4 and the baffle plate 12 by a plurality of baffle former bolts 14 shown in FIG. .
[0007]
[Problems to be solved by the invention]
By the way, in the pressurized water reactor having the above structure, when the primary cooling water flowing into the reactor core 4 is heated to a high temperature by the fuel assembly loaded in the fuel assembly loading region 11, the baffle plate 12 and Relative displacement occurs due to the thermal expansion of the former plate 13, which causes 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 lengthened, the baffle former bolt 14 interferes near the inner corner 11 a of the fuel assembly loading region 11. Problems arise.
[0008]
The present invention has been made in view of the above points, and is a pressurized water mold that can reduce the stress generated in the baffle former bolts without interfering with the baffle former bolts in the vicinity of the inner corner of the fuel assembly loading region. The purpose is to provide a nuclear reactor .
[0009]
[Means for Solving the Problems]
In order to solve the above problems, the present invention provides a core tank provided in a nuclear reactor vessel, a plurality of baffle plates that form a fuel assembly loading region inside the core tank, and these baffle plates In a pressurized water reactor having a core structure having a former plate provided between the reactor tank and a plurality of baffle former bolts for fixing the baffle plate to the former plate, the inside of the fuel assembly loading region The corner is an L-shaped corner baffle formed by cutting two baffle plates at right angles by welding or machining so that the baffle former bolts do not interfere with each other near the inner corner. And fixed.
[0010]
DETAILED DESCRIPTION OF THE INVENTION
Hereinafter, an embodiment of the present invention will be described with reference to FIG. 1, and the same parts as those shown in FIGS.
FIG. 1 is a plan view showing a part of a fuel assembly loading region 11 formed inside a reactor core 4 according to an embodiment of the present invention. As shown in FIG. The part 11 a is formed by an L-shaped square baffle 15. The angular baffle 15 is formed by out cutting by two welded baffle plate 12, 12 from each other at right angles or machining, and is fixed to the former plate 13 by the baffle former bolts 14.
[0011]
In one embodiment of the present invention described above, the fuel assembly L-shaped corners of the inner corner portion 11a is formed by out cutting by two mutually perpendicularly welded to the baffle plate 12, 12 or machining of the loading area 11 due to the baffle 15, never baffle former bolts 14 interfere with each other in the vicinity of the inner corner 11a of the fuel assembly loading area 11. Therefore, the length of the baffle former bolt 14 can be made longer than before, and thereby the stress generated in the baffle former bolt 14 can be reduced.
[0012]
Further, in the above-described embodiment, the number of baffle former bolts 14 is reduced as compared with the prior art, 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 cutting the two baffle plates 12 and 12 by welding or machining at right angles to each other. It is possible to prevent a gap from occurring in the inner corner portion 11a of the region 11, thereby preventing the occurrence of a lateral flow of cooling water that adversely affects the fuel assembly loaded in the fuel assembly loading region 11.
[0013]
【The invention's effect】
As described above, according to the present invention, it is possible to reduce the stress generated in the baffle former bolts without baffle former bolts interfere near the inner corner of the fuel assembly loading region, a baffle former since the number of bolts is reduced than conventionally possible to provide a pressurized water reactor that can be reduced in cost.
[Brief description of the drawings]
FIG. 1 is a plan view showing a part of a fuel assembly loading region formed inside a reactor core according to an embodiment of the present invention.
FIG. 2 is a longitudinal sectional view of a pressurized water reactor.
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.
4 is a cross-sectional view taken along line AA in FIG.
[Explanation of symbols]
DESCRIPTION OF SYMBOLS 1 Reactor vessel 4 Reactor tank 8 Lower core plate 9 Upper core plate 11 Fuel assembly loading area 11a Inner corner 12 Baffle plate 13 Former plate 14 Baffle former bolt 15 Square baffle

Claims (1)

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炉心構造の加圧水型原子炉において、
前記燃料集合体装荷領域の内側角部を、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形成したＬ形の角バッフルとし、上記内側角部付近で上記バッフルフォーマボルトが干渉し合うことのないようにして固定したことを特徴とする加圧水型原子炉。A reactor core provided in the reactor vessel, a plurality of baffle plates forming a fuel assembly loading region inside the reactor tank, and a former plate provided between the baffle plates and the reactor core tank, In a pressurized water reactor having a core structure having a plurality of baffle former bolts fixing the baffle plate to the former plate,
An inner corner of the fuel assembly loading region is an L-shaped square baffle formed by cutting two baffle plates at right angles to each other by welding or machining, and the baffle former bolt is located near the inner corner. A pressurized water reactor characterized by being fixed so as not to interfere with each other.
JP28442998A 1998-10-06 1998-10-06 Pressurized water reactor Expired - Lifetime JP4301604B2 (en)

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

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JP2000111682A JP2000111682A (en) 2000-04-21
JP4301604B2 true JP4301604B2 (en) 2009-07-22

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Families Citing this family (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2860640B1 (en) * 2003-10-01 2006-01-13 Framatome Anp METHOD AND DEVICE FOR PACKAGING NON-SEALED NUCLEAR FUEL PENCILS FOR TRANSPORTATION AND LONG-TERM STORAGE OR STORAGE
US8532245B2 (en) * 2008-12-17 2013-09-10 Westinghouse Electric Company Llc Core shroud corner joints
KR101102105B1 (en) 2010-06-16 2012-01-18 두산중공업 주식회사 Bonding structure for Baffle of Nuclear Reactor Head Assembly
JP7493436B2 (en) 2020-12-01 2024-05-31 三菱重工業株式会社 Analysis device, analysis method, and program

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