JPS63188794A - Cross type control rod - Google Patents
Cross type control rodInfo
- Publication number
- JPS63188794A JPS63188794A JP62022204A JP2220487A JPS63188794A JP S63188794 A JPS63188794 A JP S63188794A JP 62022204 A JP62022204 A JP 62022204A JP 2220487 A JP2220487 A JP 2220487A JP S63188794 A JPS63188794 A JP S63188794A
- Authority
- JP
- Japan
- Prior art keywords
- control rod
- length
- reactor
- neutron
- neutron instrumentation
- 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
Links
- 239000000446 fuel Substances 0.000 description 23
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 5
- 238000009835 boiling Methods 0.000 description 4
- 230000007423 decrease Effects 0.000 description 4
- 238000005259 measurement Methods 0.000 description 4
- 230000009257 reactivity Effects 0.000 description 3
- 238000001228 spectrum Methods 0.000 description 3
- 230000000712 assembly Effects 0.000 description 2
- 238000000429 assembly Methods 0.000 description 2
- 230000000694 effects Effects 0.000 description 2
- 238000000605 extraction Methods 0.000 description 2
- 241001143500 Aceraceae Species 0.000 description 1
- 238000002485 combustion reaction Methods 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 230000002452 interceptive effect Effects 0.000 description 1
- 239000000463 material Substances 0.000 description 1
- 238000000034 method Methods 0.000 description 1
- 238000012544 monitoring process Methods 0.000 description 1
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
- Fishing Rods (AREA)
- Fluid-Damping Devices (AREA)
- Forging (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】
〔産業上の利用分野〕
本発明は、原子炉の十字型制御棒に係り、特に、燃料集
合体の対角線方向に対向する二つのコーナ一部に直接隣
接するように十字型制御棒が配置されている沸騰水型原
子炉に好適な十字型制御棒に関する。DETAILED DESCRIPTION OF THE INVENTION [Field of Industrial Application] The present invention relates to a cruciform control rod for a nuclear reactor, and particularly to a cruciform control rod that is directly adjacent to a portion of two diagonally opposite corners of a fuel assembly. The present invention relates to a cross-shaped control rod suitable for a boiling water nuclear reactor in which a cross-shaped control rod is arranged.
現行の沸騰水型原子炉で利用されている燃料の取出し燃
焼度は約２５ Ｇｗｄ／ を程度であるが、現在、燃料
経済性をさらに向上させ高燃焼度化を図るために、取り
出し燃焼度７０ （、ｗｄ／ｌ 程度の高燃焼度の原
子炉（高燃焼炉）が要求されている。高燃焼炉の実現の
ためには、核分裂性物質の濃縮度を高めた燃料が使用さ
れる。濃縮度を高めると原子炉内の中性子スペクトルが
硬化する（即ち、熱中性子の割合が減り、高速中性子の
割合が増える）。The fuel extraction burnup used in current boiling water reactors is approximately 25 Gwd/, but currently, in order to further improve fuel economy and achieve high burnup, the extraction burnup is 70 Gwd/. (, wd/l) A nuclear reactor (high burnup reactor) with a high burnup is required. In order to realize a high burnup reactor, fuel with a high enrichment of fissile material is used. Increasing the temperature hardens the neutron spectrum in the reactor (ie, the proportion of thermal neutrons decreases and the proportion of fast neutrons increases).
他方、制御棒は熱中性子を吸収するものであるから、中
性子スペクトルが硬化すると制御棒価値が低下し、反応
度停止余裕が少くなるという問題が生ずる。（反応度停
止余裕とは、原子炉停止時に、最大反応度価値を持つ制
御棒１本が完全に引抜かれ、他の制御棒９吟挿入の状態
で、炉心が臨界未満であるための余裕である。）
制御棒価値を増大させるためには、２つの手段が考えら
れる。１つは、中性子スペクトル自身をソフト（熱中性
子の数が増し、高速中性子の数が減る。）にすることで
あシ、これは、燃料集合体内の水ロッドの径２本数を増
大させることにょシ実現できる。On the other hand, since the control rod absorbs thermal neutrons, the hardening of the neutron spectrum causes a problem in that the value of the control rod decreases and the margin for stopping the reactivity decreases. (Reactivity shutdown margin is the margin for the reactor core to be subcritical when the reactor is shut down, with one control rod with the highest reactivity value completely withdrawn and nine other control rods inserted. ) There are two possible ways to increase the value of control rods. One is to make the neutron spectrum itself soft (the number of thermal neutrons increases and the number of fast neutrons decreases), and this is done by increasing the number of diameter water rods in the fuel assembly. It can be realized.
他の手段は、十字型制御棒自身の翼長及び径を大きくさ
せることにより、制御棒自身の価値を増大させることで
ある。その−例として、特願昭６０−１４２４６５にお
いては、現行の沸騰水型原子炉に対して、制御棒ピッチ
（制御棒位置）は現行通シとするが、制御棒を４５°度
回転させることによりできる升目に、現行燃料の約２倍
の断面積を持つ燃料集合体を装荷させる原子炉を提案し
ている。この原子炉においては、燃料集合体の一辺の長
さが現行のものに比べ約６倍となるため、制御棒の翼長
も現行のσ倍に波長でき、しかも制御棒本数は、現行と
同数なので、炉心全体としての制御棒価値を約６倍に増
加させることができる。Another measure is to increase the value of the cruciform control rod itself by increasing its wing span and diameter. For example, in Japanese Patent Application No. 142465/1982, the control rod pitch (control rod position) is the same as the current standard for the current boiling water reactor, but the control rods are rotated 45 degrees. We are proposing a nuclear reactor in which fuel assemblies with a cross-sectional area approximately twice that of current fuel are loaded into the squares created by this method. In this reactor, the length of one side of the fuel assembly will be approximately 6 times that of the current one, so the blade length of the control rods will also be σ times the wavelength of the current one, and the number of control rods will be the same as the current one. Therefore, the value of the control rods for the entire reactor core can be increased approximately six times.
％願昭６０−１４２４６５で示す原子炉では、燃料集合
体は、対角線方向に対向する２つのコーナ部に直接隣接
する十字型の制御棒により四面を取囲まｎる。従って、
炉心内の監視及び出方分布計算等に利用される炉内中性
子計測系は、燃料集合体の対向する制御棒の存在しない
コーナ部に取付けられている。そして十字型制御棒の四
つの翼の翼長は等しく、その翼長け、この中性子計測系
と干渉しないように考慮して決定されている。In the nuclear reactor shown in Application No. 60-142465, the fuel assembly is surrounded on all sides by cross-shaped control rods directly adjacent to two diagonally opposite corners. Therefore,
The in-core neutron measurement system, which is used for monitoring the inside of the reactor core and calculating the emission distribution, is installed at a corner of the fuel assembly where no opposing control rods are present. The lengths of the four wings of the cruciform control rod are the same, and the length was determined to avoid interference with the neutron measurement system.
炉停止余裕の観点からは、高燃焼炉においては、出来得
る限り制御棒価値を大きくすることが望ましいが、上記
提案の原子炉においては、四つの相等しい翼長を持つ十
字型制御棒の翼長が中性子計測系と干渉しない長さに定
められているため、制御棒価値をそれ以上大きくするこ
とができない。From the perspective of reactor shutdown margin, it is desirable to increase the value of control rods as much as possible in high-burning reactors, but in the reactor proposed above, four cruciform control rod blades with equal blade lengths are used. Since the length of the control rod is set to a length that does not interfere with the neutron measurement system, the value of the control rod cannot be increased any further.
本発明の目的は、燃料集合体の対角方向に対向する２つ
のコーナ部に直接隣接する十字型制御棒を配置し念高燃
焼沸騰水型原子炉において、炉停止余裕を改善するため
、よシ大きい制御棒価値を有する制御棒を提供するにあ
る。An object of the present invention is to improve the reactor shutdown margin in a highly burnable boiling water reactor by arranging cross-shaped control rods directly adjacent to two diagonally opposite corners of a fuel assembly. Our aim is to provide control rods with great control rod value.
本発明は、上記タイプの原子炉において十字型制御棒の
四つの翼のうち中性子計測系と干渉しないように翼長が
制限されるのは一つの翼だけであることに着目し、他の
三つの翼、または、対称性を考慮して、他の二つの翼の
翼長を、制御棒同志が干渉しない範囲で上記一つの翼の
翼長よフ長くしたものである。The present invention focuses on the fact that among the four wings of the cruciform control rod in the above-mentioned type of nuclear reactor, only one wing is limited in length so as not to interfere with the neutron measurement system, and the other three wings are Or, in consideration of symmetry, the length of the other two wings is made longer than the length of the above-mentioned one wing to the extent that the control rods do not interfere with each other.
制御棒価値は、４つの翼長の長さの和にほぼ比例するの
で、本発明のように、中性子計装管との取合を考慮する
８安のない翼の翼長をさらに長くすることによシ制御棒
価値を高めることができる。Since the value of the control rod is approximately proportional to the sum of the lengths of the four blade lengths, as in the present invention, the blade length of the blades without the 8-bar can be further increased in consideration of connection with the neutron instrumentation tube. You can increase the value of the control rod.
第２図は前記特願昭６０−１４２４６５に記載さｎたよ
うな原子炉の炉心の一部の上面図、第３図はその炉心全
体の水平断面図であシ、図中、３は燃料集合体、１は十
字型制御棒、４は中性子計装管、１４Ｆｉ燃料集合体を
支持する格子板である。Figure 2 is a top view of a part of the core of a nuclear reactor as described in the above-mentioned Japanese Patent Application No. 60-142465, and Figure 3 is a horizontal sectional view of the entire core. In the assembly, 1 is a cross-shaped control rod, 4 is a neutron instrumentation tube, and a grid plate that supports the 14Fi fuel assembly.
燃料集合体３は、燃料集合体の対角線方向に対向する２
つのコーナ部に直接隣接する制御棒１にょシ四面を取囲
まれている。中性子計装管４は８燃料集合体に１つの割
合で炉内に均等に配置されている九め、十字型制御棒１
の四つの楓のうち１つは中性子計装管４と隣接すること
になる。第４図は中性子計装管４の支持構造を示す鉛直
断面図であって、原子炉炉心の下部タイプレート７近傍
での拡大図である。第４図に示すように、下部タイグレ
ート７より下部では、中性子計装管４は中性子計装案内
管６により支持されている。中性子計装案内管６の外径
は約４８認であり、中性子計装管４の外径は約１７餌で
ある。The fuel assembly 3 has two parts facing each other in the diagonal direction of the fuel assembly.
The control rod 1 directly adjacent to the two corners is surrounded on all sides. The neutron instrumentation tube 4 is a ninth, cross-shaped control rod 1 that is evenly arranged in the reactor at a ratio of one for every eight fuel assemblies.
One of the four maples will be adjacent to the neutron instrumentation tube 4. FIG. 4 is a vertical sectional view showing the support structure of the neutron instrumentation tube 4, and is an enlarged view of the vicinity of the lower tie plate 7 of the reactor core. As shown in FIG. 4, below the lower tie plate 7, the neutron instrumentation tube 4 is supported by a neutron instrumentation guide tube 6. The outer diameter of the neutron instrumentation guide tube 6 is about 48 mm, and the outer diameter of the neutron instrumentation tube 4 is about 17 mm.
前述し友ように、特願昭６０−１４２４６５記載の原子
炉においては、十字型制御棒ｌの四つの翼の翼長（十字
型制御棒の横断面において十字の中心から翼の側端縁ま
での長さ）は相等しく作られており、その翼長は中性子
計装管４や中性子計装案内管６に干渉しないような長さ
に定められていた。As mentioned above, in the nuclear reactor described in Japanese Patent Application No. 60-142465, the length of the four wings of the cruciform control rod L (from the center of the cross to the side edge of the wing in the cross section of the cruciform control rod) is The blades were made to have the same length), and the blade span was set to a length that would not interfere with the neutron instrumentation tube 4 or the neutron instrumentation guide tube 6.
これに対して１本発明実施例の十字型制御棒１は、第１
図に示すように、中性子計装管４に隣接する翼ＩＡ及び
それと反対側罠延びる翼ＩＡの翼長は中性子計装管４（
および中性子計装案内管６）と干渉しない長さに定めら
れているが、それと直角方向の翼ＩＢ（中性子計装管４
や中性子計装案内管６に隣接しない翼）の翼長け、制御
棒同志が干渉しない範囲において、よシ長く作られてい
る。On the other hand, the cross-shaped control rod 1 according to the embodiment of the present invention has a first
As shown in the figure, the blade length of the wing IA adjacent to the neutron instrumentation tube 4 and the wing IA extending from the opposite side are the neutron instrumentation tube 4 (
and neutron instrumentation guide tube 6), but the blade IB (neutron instrumentation tube 4) is perpendicular to it.
The blades (and the blades not adjacent to the neutron instrumentation guide tube 6) are made long enough to prevent the control rods from interfering with each other.
第５図は一体の燃料集合体３の囲りの拡大図であり、本
発明実施例の制御棒と前記特願昭６０−１４２４６５記
載の制御棒との比較を示す。同図で、燃料集合体３の対
角線方向に対向する２つのコーナ部には、直接隣接する
制御棒１が配置されている。ここで、斜線で示している
のが上記後者の制御棒であシ、斜線部に、破線で示し７
’ｊＡの部分を追加したのが本発明実施例の制御棒であ
る。FIG. 5 is an enlarged view of the integral fuel assembly 3, and shows a comparison between the control rod according to the embodiment of the present invention and the control rod described in the above-mentioned Japanese Patent Application No. 142,465/1982. In the figure, directly adjacent control rods 1 are arranged at two diagonally opposite corners of the fuel assembly 3. Here, the latter control rod is indicated by diagonal lines, and the dashed line indicates 7.
The control rod according to the embodiment of the present invention has the added part 'jA.
中性子計装管４は、制御棒の隣接しない１つのコーナ部
に配置されている。The neutron instrumentation tube 4 is arranged at one non-adjacent corner of the control rod.
第５図において、燃料集合体を含む格子幅は、約２１９
−であるが、中性子計装管４および中性子計装案内管６
に隣接する制御棒の１つの翼の翼長は、中性子計装管４
゛との取合い（実際には、下部タイプレートより下部で
の制御棒案内管と中性子計装案内管６との取合い）によ
シ、約１７７ｍに制限される。In FIG. 5, the lattice width including the fuel assembly is approximately 219
-, but the neutron instrumentation tube 4 and the neutron instrumentation guide tube 6
The wing span of one wing of the control rod adjacent to the neutron instrumentation tube 4
The length is limited to approximately 177 m due to the connection between the control rod guide tube and the neutron instrumentation guide tube 6 below the lower tie plate.
第６図に、制御棒の翼長と炉停止余裕の関係を示す。同
図では前記特願記載の制御棒（翼長＝１７７ ｗａｓ
）を基準として、示しである。本発明実施例では第２図
において中性子計装管がない個所では、同図のＡに相当
する長さだけ翼長を長くする。この場合、中性子計装管
に隣接しない翼ＩＢを約１９６ｍまで長くすることがで
きる。Figure 6 shows the relationship between control rod blade length and reactor shutdown margin. In the same figure, the control rod (blade length = 177 was
) is the standard. In the embodiment of the present invention, in FIG. 2, where there is no neutron instrumentation tube, the blade length is increased by a length corresponding to A in the figure. In this case, the wing IB that is not adjacent to the neutron instrumentation tube can be up to about 196 m long.
第１図に示す本発明実施例の制御棒において、中性子計
装管４に隣接する一対の翼ＩＡの長さは約１７７＋ａＩ
であシ、他の一対の翼ＩＢの長さは約１９６ｍである。In the control rod according to the embodiment of the present invention shown in FIG. 1, the length of the pair of wings IA adjacent to the neutron instrumentation tube 4 is approximately 177+aI.
The length of the other pair of wings IB is approximately 196 m.
また、翼の厚さは約６．６ ｍとする。ここで、燃料集
合体３を含む格子幅は約２１９露であり、燃料集合体の
一辺の長さは、約２１３鰭とする。本発明実施例の制御
棒を用いることにより、第６図より、約１．０チ炉停止
余裕が緩和されることがわかる。Also, the thickness of the blade is approximately 6.6 m. Here, the lattice width including the fuel assembly 3 is about 219 fins, and the length of one side of the fuel assembly is about 213 fins. It can be seen from FIG. 6 that by using the control rod of the embodiment of the present invention, the reactor shutdown margin is reduced by about 1.0 degrees.
以上の実施例においては、対称性を保つために、対向す
る一対の翼の長さのみを長くしたが、中性子計装管に隣
接しない他の３つの翼長を長くシ次制御棒も可能である
。In the above example, in order to maintain symmetry, only the length of the opposing pair of blades was lengthened, but it is also possible to lengthen the other three blades that are not adjacent to the neutron instrumentation tube. be.
また以上の実施例においては、翼の厚さは４つの翼とも
同じ厚さとしているが、各具の制御棒価値及び重量の均
質化のため、翼長が短かい一対の翼の厚さを厚くするこ
とも考えられる。In addition, in the above embodiment, the thickness of the four blades is the same, but in order to homogenize the control rod value and weight of each component, the thickness of the pair of blades with a short blade length is changed. It is also possible to make it thicker.
本光明の制御棒は、燃料集合体の対角線方向に対向する
２つのコーナ部に直接隣接するように制御棒が配置され
ている高燃焼炉に適用することにより、制御棒価値をよ
シ高め、炉停止余裕をより緩和することが可能である。The control rod of this Komei increases the value of the control rod by applying it to a high combustion reactor where the control rod is arranged directly adjacent to two diagonally opposite corners of the fuel assembly. It is possible to further reduce the margin for reactor shutdown.
第１図は本発明の一実施例を示す部分断面図、第２図は
燃料集合体の対角線方向に対向する二つのコーナ部に直
接隣接するように制御棒が配置されている原子炉炉心の
部分の上面因、第３図は該炉心の全体横断面図、第４図
は中性子計装管の支持構造を示す鉛直断面図、第５図は
第３図の部分拡大図、第６図は制御棒の翼長と炉停止余
裕との関係を示す図、である。
１・・・十字型制御棒、 ３・・・燃料集合体。
４・・・中性子計装管、 ６・・・中性子計装案内管、
７・・・下部タイグレート。FIG. 1 is a partial cross-sectional view showing an embodiment of the present invention, and FIG. 2 is a nuclear reactor core in which control rods are arranged directly adjacent to two diagonally opposite corners of a fuel assembly. Figure 3 is a cross-sectional view of the entire core, Figure 4 is a vertical cross-sectional view showing the support structure of the neutron instrumentation tube, Figure 5 is a partially enlarged view of Figure 3, and Figure 6 is a partial cross-sectional view of the core. FIG. 3 is a diagram showing the relationship between control rod blade length and reactor shutdown margin. 1...Cross-shaped control rod, 3...Fuel assembly. 4... Neutron instrumentation tube, 6... Neutron instrumentation guide tube,
7...Lower tie rate.
Claims (1)
翼長が、それと直交する翼の翼長よりも短いことを特徴
とする十字型制御棒。 ２、対向する翼の翼長がそれと直交する翼の翼長よりも
短い特許請求の範囲第１項記載の十字型制御棒。 ３、翼長の短い翼の厚さを翼長の長い翼の厚さよりも厚
くした特許請求の範囲第１項又は第２項記載の十字型制
御棒。[Claims] 1. A cruciform control rod characterized in that the length of at least one of the four wings of the cruciform control rod is shorter than the length of the wing orthogonal thereto. 2. The cruciform control rod according to claim 1, wherein the blade length of the opposing blade is shorter than the blade length of the blade perpendicular thereto. 3. The cruciform control rod according to claim 1 or 2, wherein the thickness of the short blades is greater than the thickness of the long blades.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP62022204A JPS63188794A (en) | 1987-02-02 | 1987-02-02 | Cross type control rod |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP62022204A JPS63188794A (en) | 1987-02-02 | 1987-02-02 | Cross type control rod |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPS63188794A true JPS63188794A (en) | 1988-08-04 |
Family
ID=12076261
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP62022204A Pending JPS63188794A (en) | 1987-02-02 | 1987-02-02 | Cross type control rod |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS63188794A (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2001201582A (en) * | 2000-01-19 | 2001-07-27 | General Electric Co <Ge> | Fuel bundle/control rod assembly for reactor |
-
1987
- 1987-02-02 JP JP62022204A patent/JPS63188794A/en active Pending
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2001201582A (en) * | 2000-01-19 | 2001-07-27 | General Electric Co <Ge> | Fuel bundle/control rod assembly for reactor |
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