JP2000137089A - Core structure of pressurized water reactor - Google Patents

Core structure of pressurized water reactor

Info

Publication number
JP2000137089A
JP2000137089A JP10310490A JP31049098A JP2000137089A JP 2000137089 A JP2000137089 A JP 2000137089A JP 10310490 A JP10310490 A JP 10310490A JP 31049098 A JP31049098 A JP 31049098A JP 2000137089 A JP2000137089 A JP 2000137089A
Authority
JP
Japan
Prior art keywords
core tank
plate
core
bolt
former
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
Application number
JP10310490A
Other languages
Japanese (ja)
Other versions
JP3886654B2 (en
Inventor
Noboru Kubo
登 久保
Hirokazu Shomura
浩和 庄村
Kenji Umeda
賢治 梅田
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.)
Mitsubishi Heavy Industries Ltd
Original Assignee
Mitsubishi Heavy Industries Ltd
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 Mitsubishi Heavy Industries Ltd filed Critical Mitsubishi Heavy Industries Ltd
Priority to JP31049098A priority Critical patent/JP3886654B2/en
Publication of JP2000137089A publication Critical patent/JP2000137089A/en
Application granted granted Critical
Publication of JP3886654B2 publication Critical patent/JP3886654B2/en
Anticipated expiration legal-status Critical
Expired - Lifetime 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

Abstract

PROBLEM TO BE SOLVED: To facilitate ultrasonic inspection of a bolt fixing a core tank with a former plate by fixing the former plate positioned on the back side of a thermal shield together with a buffle plate to the core tank by a bolt from the inside. SOLUTION: In the core tank 4 of a pressurized water reactor, a former plate 13 positioned on the back side of a thermal shield 15 together with a buffle plate 11 are fixed to a core tank 4 by a long bolt 18 from the inside of the core tank 4. By such construction, ultrasonic inspection of the bolt 18 can be executed from the inside of the core tank 4, and because the thermal shield 15 is unnecessary to be detached from the core tank 4, the labor and the time required for detaching or fitting the thermal shield 15 can be omitted. Further by bolt cooling holes 19 formed on the upper face and the lower face of the former plate 13, the bolt 18 is cooled by primary cooling water, the bolt 18 can be prevented from thermally fixing to the threaded part of the bolt hole formed on the former plate 13.

Description

【発明の詳細な説明】DETAILED DESCRIPTION OF THE INVENTION

【0001】[0001]

【発明の属する技術分野】本発明は、加圧水型原子炉の
炉心構造に関するものである。
BACKGROUND OF THE INVENTION 1. Field of the Invention 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5に示さ
れる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 core 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、燃料集
合体16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 tank 4 has a cylindrical shape, and a plurality of control rod cluster guides for guiding control rod clusters into a fuel assembly 16 are provided on an upper core support plate 5 closing the upper end of the core tank 4. A tube 6 is attached. The core tank 4 defines an annular downcomer 7 with 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. Thus, it flows into the core tank 4 from the lower end of the core tank 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】また、炉心槽4の内部には複数のバッフル
プレート11が下部炉心板8と上部炉心板9との間に設
けられている。これらのバッフルプレート11は炉心槽
4の内側に燃料集合体装荷領域を画成するものであっ
て、複数本のバッフルフォーマボルト12(図6参照)
によってフォーマプレート13に固定されている。
A plurality of baffle plates 11 are provided between the lower core plate 8 and the upper core plate 9 inside the core tank 4. These baffle plates 11 define a fuel assembly loading area inside the core tank 4 and include a plurality of baffle former bolts 12 (see FIG. 6).
Is fixed to the former plate 13.

【0006】フォーマプレート13はバッフルプレート
11と炉心槽4との間に燃料集合体非装荷領域を画成す
るものであって、バッフルプレート11と炉心槽4との
間に互いに間隔を存して水平に配設されている。また、
フォーマプレート13は、図6に示すように、多数本の
バレルフォーマボルト14によって炉心槽4に炉心槽4
の外側から固定されている。
The former plate 13 defines a fuel assembly non-loading region between the baffle plate 11 and the core tank 4, and is spaced apart from the baffle plate 11 and the core tank 4. It is arranged horizontally. Also,
As shown in FIG. 6, the former plate 13 is connected to the core tank 4 by a number of barrel former bolts 14.
Is fixed from the outside.

【0007】一方、炉心槽4の外側には厚手の鋼板から
なる複数の熱遮蔽体15が設けられている。これらの熱
遮蔽体15は上述した燃料装荷領域に装荷された燃料集
合体16(図5参照)の中で炉心槽4の近傍に位置する
燃料集合体16の側面を炉心槽4の外側から熱遮蔽する
ものであって、図6に示す複数本のボルト17によって
炉心槽4の外周面に固定されている。
On the other hand, a plurality of heat shields 15 made of a thick steel plate are provided outside the core vessel 4. These heat shields 15 heat the side surfaces of the fuel assemblies 16 located near the core tank 4 from the outside of the core tank 4 in the fuel assemblies 16 (see FIG. 5) loaded in the fuel loading region described above. It is shielded, and is fixed to the outer peripheral surface of the core vessel 4 by a plurality of bolts 17 shown in FIG.

【0008】ところで、このような構造の加圧水型原子
炉では、原子炉容器1の内部を定期的に検査することが
義務付けられている。このため、上述したバレルフォー
マボルト14を超音波検査する場合には、原子炉容器1
から炉心槽4を取り出して仮置スタンドに仮置した状態
で炉心槽外周面に超音波検査装置を吊り降ろしてバレル
フォーマボルト14の超音波検査を行っている。
Incidentally, in the pressurized water reactor having such a structure, it is required to periodically inspect the inside of the reactor vessel 1. Therefore, when the barrel former bolt 14 described above is subjected to ultrasonic inspection, the reactor vessel 1
The ultrasonic inspection of the barrel former bolt 14 is performed by suspending the ultrasonic inspection apparatus on the outer peripheral surface of the core tank while taking out the core tank 4 from the core tank 4 and temporarily placing the core tank 4 on a temporary holding stand.

【0009】[0009]

【発明が解決しようとする課題】しかしながら、一部の
バレルフォーマボルト14は熱遮蔽体15の裏側にある
ため、全てのバレルフォーマボルト14を超音波検査す
るためには、炉心槽4から熱遮蔽体15を取り外す必要
がある。このため、熱遮蔽体15の取り外しや取り付け
に手間がかかり、フォーマプレート13を炉心槽4に固
定するボルトの超音波検査に多くの時間と費用とを要す
る。
However, since some of the barrel former bolts 14 are located behind the heat shield 15, in order to ultrasonically inspect all the barrel former bolts 14, the heat shield from the core tank 4 is required. The body 15 needs to be removed. For this reason, it takes time and effort to remove and attach the heat shield 15, and ultrasonic inspection of the bolts for fixing the former plate 13 to the core tank 4 requires much time and cost.

【0010】本発明は、上記の点に鑑みてなされたもの
であって、炉心槽とフォーマプレートとを固定するボル
トの超音波検査を容易に行うことが可能な加圧水型原子
炉の炉心構造を提供することを目的とするものである。
The present invention has been made in view of the above points, and has an object to provide a core structure of a pressurized water nuclear reactor capable of easily performing an ultrasonic inspection of bolts for fixing a core tank and a former plate. It is intended to provide.

【0011】[0011]

【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、請求項1の発明は、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画成
する複数のバッフルプレートと、このバッフルプレート
と前記炉心槽との間に燃料集合体非装荷領域を画成する
複数のフォーマプレートと、前記燃料集合体装荷領域に
装荷された燃料集合体のうち前記炉心槽の近傍に位置す
る燃料集合体の側面を前記炉心槽の外側から熱遮蔽する
熱遮蔽体とを有する加圧水型原子炉において、前記熱遮
蔽体の裏側に位置する前記フォーマプレートをボルトに
よって前記バッフルプレートと共に前記炉心槽に前記炉
心槽の内側から固定したことを特徴とする。
In order to solve the above-mentioned problems, the invention of claim 1 defines a core tank provided in a reactor vessel and a fuel assembly loading area inside the core tank. A plurality of baffle plates, a plurality of former plates defining a fuel assembly non-loading region between the baffle plate and the core tank, and a fuel assembly loaded in the fuel assembly loading region. In a pressurized water reactor having a heat shield for thermally shielding the side surface of the fuel assembly located near the core tank from the outside of the core tank, the former plate located on the back side of the heat shield is bolted. The core tank is fixed to the core tank together with the baffle plate from the inside of the core tank.

【0012】[0012]

【発明の実施の形態】以下、図1乃至図4を参照して本
発明の一実施形態について説明するが、図5および図6
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係る加圧水型原子炉の
炉心構造を示す図で、図2は図1のA−A線に沿う断面
図である。同図に示すように、熱遮蔽体15の裏側に位
置するフォーマプレート13は、長尺のボルト18によ
ってバッフルプレート11と共に炉心槽4に炉心槽4の
内側から固定されている。
DETAILED DESCRIPTION OF THE PREFERRED EMBODIMENTS One embodiment of the present invention will be described below with reference to FIGS.
The same parts as those shown in FIG. FIG. 1 is a diagram showing a core structure of a pressurized water reactor according to one embodiment of the present invention, and FIG. 2 is a cross-sectional view taken along line AA of FIG. As shown in the figure, the former plate 13 located on the back side of the heat shield 15 is fixed to the core tank 4 together with the baffle plate 11 from the inside of the core tank 4 by long bolts 18.

【0013】一方、熱遮蔽体15の裏側に位置しないフ
ォーマプレート13は、従来と同様に、バレルフォーマ
ボルト14によって炉心槽4に炉心槽4の外側から固定
されている。
On the other hand, the former plate 13 which is not located on the back side of the heat shield 15 is fixed to the core tank 4 from the outside of the core tank 4 by barrel former bolts 14 as in the prior art.

【0014】図3は図1のB−B線に沿う断面図であ
り、同図に示すようにフォーマプレート13の上面と下
面には、フォーマプレート13にねじ込まれたボルト1
2,14,18を一次冷却水により冷却するためのボル
ト冷却孔19が形成されている。
FIG. 3 is a sectional view taken along the line BB of FIG. 1. As shown in FIG. 3, the bolt 1 screwed into the former plate 13 is provided on the upper and lower surfaces of the former plate 13.
Bolt cooling holes 19 for cooling the cooling water 2, 14, 18 with primary cooling water are formed.

【0015】図4は図1のC−C線に沿う断面図であ
り、同図に示すようにフォーマプレート13には、フォ
ーマプレート13を一次冷却水により冷却するためのフ
ォーマ冷却孔20がバッフルプレート11の近傍に一定
ピッチで穿設されている。
FIG. 4 is a sectional view taken along the line CC of FIG. 1. As shown in FIG. 4, the former plate 13 has a baffle for cooling the former plate 13 with primary cooling water. It is drilled at a constant pitch near the plate 11.

【0016】上述した本発明の一実施形態では、熱遮蔽
体15の裏側に位置するフォーマプレート13が長尺の
ボルト18によってバッフルプレート11と共に炉心槽
4に炉心槽4の内側から固定されているため、熱遮蔽体
15の裏側に位置するボルト18については炉心槽4の
内側から超音波音波検査を行うことができる。従って、
本発明の一実施形態では炉心槽4とフォーマプレート1
3とを固定するボルト14,18の超音波検査を行う際
に熱遮蔽体15を炉心槽4から取り外す必要がないの
で、熱遮蔽体15の取り外しや取り付けに要する手間と
時間を省略でき、炉心槽4とフォーマプレート13とを
固定するボルト14,18の超音波検査を容易に行うこ
とができる。
In the embodiment of the present invention described above, the former plate 13 located on the back side of the heat shield 15 is fixed to the core tank 4 together with the baffle plate 11 from the inside of the core tank 4 by long bolts 18. Accordingly, the ultrasonic inspection can be performed on the bolt 18 located on the back side of the heat shield 15 from the inside of the core tank 4. Therefore,
In one embodiment of the present invention, the core tank 4 and the former plate 1
Since it is not necessary to remove the heat shield 15 from the core tank 4 when performing an ultrasonic inspection of the bolts 14 and 18 for fixing the heat shield 3, the trouble and time required for removing and attaching the heat shield 15 can be omitted. Ultrasonic inspection of the bolts 14 and 18 for fixing the tank 4 and the former plate 13 can be easily performed.

【0017】また、上述した実施形態ではフォーマプレ
ート13にねじ込まれたボルト12,14,18を一次
冷却水により冷却するためのボルト冷却孔19がフォー
マプレート13に形成されているため、フォーマプレー
ト13にねじ込まれたボルト12,14,18がフォー
マプレート13に形成されたボルト孔のねじ部に熱によ
って固着することを防止できる。
In the above-described embodiment, since the bolt cooling holes 19 for cooling the bolts 12, 14, and 18 screwed into the former plate 13 with the primary cooling water are formed in the former plate 13, the former plate 13 is formed. The bolts 12, 14, 18 screwed into the former plate 13 can be prevented from being fixed to the threaded portion of the bolt hole formed in the former plate 13 by heat.

【0018】さらに、上述した実施形態ではフォーマプ
レート13を一次冷却水により冷却するためのフォーマ
冷却孔20がフォーマプレート13に形成されているた
め、フォーマ冷却孔20内を流通する一次冷却水によっ
てフォーマプレート13を冷却することができる。な
お、本発明は上述した実施形態に限定されるものではな
く、特許請求の範囲に記載された要旨を逸脱しない範囲
内で種々の変形等が実施可能である。
Further, in the above-described embodiment, since the former cooling holes 20 for cooling the former plate 13 by the primary cooling water are formed in the former plate 13, the former cooling water flowing through the former cooling holes 20 is used to form the former cooling water. The plate 13 can be cooled. Note that the present invention is not limited to the above-described embodiment, and various modifications and the like can be made without departing from the gist described in the claims.

【0019】[0019]

【発明の効果】以上説明したように、本発明によれば、
炉心槽とフォーマプレートとを固定するボルトの超音波
検査を容易に行うことが可能な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,
A core structure of a pressurized water reactor capable of easily performing an ultrasonic inspection of a bolt for fixing a core tank and a former plate can be provided.

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

【図1】本発明の一実施形態に係る加圧水型原子炉の炉
心構造を示す平面図である。
FIG. 1 is a plan view showing a core structure of a pressurized water reactor according to an embodiment of the present invention.

【図2】図1のA−Aに沿う断面図である。FIG. 2 is a sectional view taken along line AA of FIG.

【図3】図1のB−Bに沿う断面図である。FIG. 3 is a sectional view taken along line BB in FIG. 1;

【図4】図1のC−Cに沿う断面図である。FIG. 4 is a sectional view taken along the line CC of FIG. 1;

【図5】加圧水型原子炉の縦断面図である。FIG. 5 is a longitudinal sectional view of a pressurized water reactor.

【図6】従来例の炉心構造を示す図である。FIG. 6 is a view showing a conventional core structure.

【符号の説明】[Explanation of symbols]

1 原子炉容器 2 入口ノズル 3 出口ノズル 4 炉心槽 6 制御棒クラスタ案内管 8 下部炉心板 9 上部炉心板 11 バッフルプ
レート 13 フォーマプレート 15 熱遮蔽体 18 ボルト 19 ボルト冷
却孔 20 フォーマ冷却孔
DESCRIPTION OF SYMBOLS 1 Nuclear reactor 2 Inlet nozzle 3 Outlet nozzle 4 Core tank 6 Control rod cluster guide tube 8 Lower core plate 9 Upper core plate 11 Baffle plate 13 Former plate 15 Thermal shield 18 Bolt 19 Volt cooling hole 20 Former cooling hole

Claims (1)

【特許請求の範囲】[Claims] 【請求項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画成する複数の
バッフルプレートと、このバッフルプレートと前記炉心
槽との間に燃料集合体非装荷領域を画成する複数のフォ
ーマプレートと、前記燃料集合体装荷領域に装荷された
燃料集合体のうち前記炉心槽の近傍に位置する燃料集合
体の側面を前記炉心槽の外側から熱遮蔽する熱遮蔽体と
を有する加圧水型原子炉において、 前記熱遮蔽体の裏側に位置する前記フォーマプレートを
ボルトによって前記バッフルプレートと共に前記炉心槽
に前記炉心槽の内側から固定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 defining a fuel assembly loading region inside the core tank, and a fuel between the baffle plate and the core tank. A plurality of former plates that define an assembly non-loading region, and a side surface of a fuel assembly located in the vicinity of the core tank among the fuel assemblies loaded in the fuel assembly loading region, from the outside of the core tank. A pressurized water reactor having a heat shield for heat shielding, wherein the former plate located on the back side of the heat shield is fixed to the core tank together with the baffle plate by bolts from inside the core tank. Core structure of a pressurized water reactor.
JP31049098A 1998-10-30 1998-10-30 Core structure of pressurized water reactor Expired - Lifetime JP3886654B2 (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP31049098A JP3886654B2 (en) 1998-10-30 1998-10-30 Core structure of pressurized water reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP31049098A JP3886654B2 (en) 1998-10-30 1998-10-30 Core structure of pressurized water reactor

Publications (2)

Publication Number Publication Date
JP2000137089A true JP2000137089A (en) 2000-05-16
JP3886654B2 JP3886654B2 (en) 2007-02-28

Family

ID=18005869

Family Applications (1)

Application Number Title Priority Date Filing Date
JP31049098A Expired - Lifetime JP3886654B2 (en) 1998-10-30 1998-10-30 Core structure of pressurized water reactor

Country Status (1)

Country Link
JP (1) JP3886654B2 (en)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US7098844B2 (en) 1999-06-14 2006-08-29 Escort Inc. Acceleration detector with integral vehicle parameter display using a vehicle interface
KR101624828B1 (en) 2015-01-02 2016-05-26 한전케이피에스 주식회사 Barrel Former Bolt Inspection Device

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US7098844B2 (en) 1999-06-14 2006-08-29 Escort Inc. Acceleration detector with integral vehicle parameter display using a vehicle interface
US7397416B2 (en) 1999-06-14 2008-07-08 Escort Inc. Police radar/laser detector with integral vehicle parameter display using a vehicle interface
KR101624828B1 (en) 2015-01-02 2016-05-26 한전케이피에스 주식회사 Barrel Former Bolt Inspection Device

Also Published As

Publication number Publication date
JP3886654B2 (en) 2007-02-28

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