JPS6223273B2 - - Google Patents
Info
- Publication number
- JPS6223273B2 JPS6223273B2 JP52143859A JP14385977A JPS6223273B2 JP S6223273 B2 JPS6223273 B2 JP S6223273B2 JP 52143859 A JP52143859 A JP 52143859A JP 14385977 A JP14385977 A JP 14385977A JP S6223273 B2 JPS6223273 B2 JP S6223273B2
- Authority
- JP
- Japan
- Prior art keywords
- fuel
- neutron
- control rod
- rod
- rods
- 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.)
- Expired
Links
- 239000000446 fuel Substances 0.000 claims description 31
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 16
- 230000000712 assembly Effects 0.000 claims description 10
- 238000000429 assembly Methods 0.000 claims description 10
- 238000009835 boiling Methods 0.000 claims description 3
- 230000000694 effects Effects 0.000 description 6
- 229910052770 Uranium Inorganic materials 0.000 description 4
- 238000010586 diagram Methods 0.000 description 3
- 238000010521 absorption reaction Methods 0.000 description 2
- OOAWCECZEHPMBX-UHFFFAOYSA-N oxygen(2-);uranium(4+) Chemical compound [O-2].[O-2].[U+4] OOAWCECZEHPMBX-UHFFFAOYSA-N 0.000 description 2
- FCTBKIHDJGHPPO-UHFFFAOYSA-N uranium dioxide Inorganic materials O=[U]=O FCTBKIHDJGHPPO-UHFFFAOYSA-N 0.000 description 2
- 238000012935 Averaging Methods 0.000 description 1
- 239000000463 material Substances 0.000 description 1
- 230000009257 reactivity Effects 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
- Monitoring And Testing Of Nuclear Reactors (AREA)
Description
【発明の詳細な説明】
本発明は稠密に配された多数の燃料集合体をも
つて構成する沸騰水原子炉に係わり特に集合体内
の出力分布を平均化した原子炉の改良に関する。DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a boiling water nuclear reactor constituted by a large number of densely arranged fuel assemblies, and particularly to an improvement of a nuclear reactor in which the power distribution within the assemblies is averaged.
従来の沸騰水型原子炉では第１図に示すように
燃料集合体１間に水ギヤツプ４と称する軽水だけ
の領域をもうけている。この水ギヤツプ４は十字
形の制御棒２の通路、中性子検出器（図示せず）
の設置場所及び、中性子減速効果の増大による反
応度利得などの役割をもたせている。 In a conventional boiling water reactor, as shown in FIG. 1, a region containing only light water, called a water gap 4, is provided between fuel assemblies 1. This water gap 4 is a passage for the cross-shaped control rod 2, and a neutron detector (not shown).
It also plays a role in increasing reactivity gain by increasing the neutron moderation effect.
ところが、この減速効果の大きい軽水を水ギヤ
ツプ４に大きく偏在させることによつて、相対的
に燃料集合体１中の減速効果が悪く、それ故、水
ギヤツプ４の部分の熱中性子レベルが燃料集合体
１内部より高くなり、従つて、水ギヤツプ４に面
した燃料棒３の出力が内部の燃料棒３の出力より
高くなる傾向にある。従来はその為に水ギヤツプ
４に面した燃料棒３の二酸化ウラン濃縮度を内部
より下げて配していたが、制御棒２が挿入された
ときは、水ギヤツプ４中の軽水が排水されるため
出力分布は制御棒２と反対側の水ギヤツプ４にピ
ークが出ることになり、出力分布の平均化の上で
好ましくなかつた。 However, by unevenly distributing this light water with a large deceleration effect in the water gap 4, the deceleration effect in the fuel assembly 1 is relatively poor, and therefore the thermal neutron level in the water gap 4 is lower than that of the fuel assembly. Therefore, the output of the fuel rods 3 facing the water gap 4 tends to be higher than the output of the fuel rods 3 inside. Conventionally, for this reason, the uranium dioxide enrichment of the fuel rod 3 facing the water gap 4 was lowered than that inside, but when the control rod 2 is inserted, the light water in the water gap 4 is drained. Therefore, the power distribution has a peak at the water gap 4 on the opposite side from the control rod 2, which is not desirable in terms of averaging the power distribution.
本発明は上記した従来技術の欠点をなくし、出
力分布の平坦化を達成することのできる原子炉を
得ることを目的とする。すなわち、本発明の原子
炉は正方格子のコーナー部に燃料棒を配しない燃
料集合体をもつて炉心を構成し、前記コーナー部
に制御棒及び中性子計装系、中性子源等を配する
ことを特徴とするものである。 An object of the present invention is to eliminate the drawbacks of the prior art described above and to obtain a nuclear reactor that can flatten the power distribution. That is, the nuclear reactor of the present invention has a core configured with fuel assemblies without fuel rods arranged in the corners of a square lattice, and control rods, a neutron instrumentation system, a neutron source, etc. are arranged in the corners. This is a characteristic feature.
以下図面を参照して本発明の一実施例を説明す
る。 An embodiment of the present invention will be described below with reference to the drawings.
第２図に示す如く本発明の原子炉は、燃料集合
体１０、制御棒２０、中性子源又は中性子計装管
３０とから構成される。 As shown in FIG. 2, the nuclear reactor of the present invention is comprised of a fuel assembly 10, a control rod 20, and a neutron source or neutron instrumentation tube 30.
前記燃料集合体１０は、正方格子状に配される
がコーナー部には配されない複数本（従来に比べ
て本数は少ない、例えば４×４、５×５、６×
６）の燃料棒１１と、この燃料棒１１を覆う八角
形状のチヤンネルボツクス１２とから構成され
る。前記複数本の燃料棒１１の中性子増倍物質で
ある二酸化ウラン（UO2）は、全て同一の濃縮度
である。 The fuel assemblies 10 are arranged in a square lattice shape, but a plurality of fuel assemblies 10 are not arranged at the corners (the number is smaller than in the past, for example, 4×4, 5×5, 6×
6) and an octagonal channel box 12 that covers the fuel rod 11. Uranium dioxide (UO 2 ), which is a neutron multiplier material in the plurality of fuel rods 11, all have the same enrichment degree.
前記制御棒２０は断面円形の棒状体で原則とし
て４体の燃料集合体１０を１単位としてみるとき
燃料集合体のコーナー部が相隣接して形成する９
つの空所２１のうち８つの空所（図では外周）に
単独にて上下動自在に配される。残りの１つの空
所（図では中央）には、中性子源又は中性子計装
管３０が配される。中性子源又は中性子計装管３
０は制御棒２０と同様断面円形の棒状部材であ
る。なお、燃料集合体のコーナ部が相隣接して形
成される空所は水対ウラン体積比分布を均一化さ
せるために必要最小限に制限されている。 The control rod 20 is a rod-shaped body with a circular cross section, and in principle, when four fuel assemblies 10 are considered as one unit, the corner portions of the fuel assemblies are formed adjacent to each other.
It is individually arranged in eight of the eight spaces 21 (outer periphery in the figure) so as to be vertically movable. A neutron source or neutron instrumentation tube 30 is placed in the remaining space (in the center in the figure). Neutron source or neutron instrumentation tube 3
0 is a rod-shaped member having a circular cross section like the control rod 20. Note that the spaces formed by adjacent corner portions of the fuel assembly are limited to the necessary minimum in order to equalize the water-to-uranium volume ratio distribution.
このように構成されているため、従来の原子炉
に比べ局所的な水対ウラン体積比分布が一定にな
る。すなわち局所的な水対ウラン体積比が、従来
は水ギヤツプの存在によつて偏つていたものを無
くすことができる。この局所的な水対ウラン体積
比が一定になることによつて、軽水による中性子
減速効果が均一化され出力分布の平坦化が達成で
きる。さらには断面円形の棒状体の制御棒は上下
動自在に配されているので原子炉出力調整時にお
いて、１本ずつ炉心内から移動させることがで
き、炉心内の出力の微調整が容易に実施すること
ができる。 Because of this configuration, the local water-to-uranium volume ratio distribution is more constant than in conventional nuclear reactors. That is, the local water-to-uranium volume ratio, which was conventionally biased due to the presence of a water gap, can be eliminated. By keeping this local water-to-uranium volume ratio constant, the neutron moderating effect of light water is made uniform, and a flattening of the power distribution can be achieved. Furthermore, the control rods, which are rod-shaped bodies with a circular cross section, are arranged so that they can move up and down, so when adjusting the reactor output, they can be moved one by one from inside the reactor core, making it easy to fine-tune the output inside the reactor core. can do.
以上説明のように本発明の原子炉は、従来の燃
料集合体あたりの燃料棒本数を減らした燃料集合
体と、大きな中性子吸収効果をもつ偏在した十字
形制御棒のかわりに、各々は比較的小さな中性子
吸収効果を持ち分散して数多く配された制御棒と
から構成されているため原子炉の出力分布を平坦
化できる。この結果は集合体を形成する燃料棒の
UO2濃度は１又は２種類で十分になる。 As explained above, the nuclear reactor of the present invention has a fuel assembly with a reduced number of fuel rods per fuel assembly, and instead of unevenly distributed cruciform control rods that have a large neutron absorption effect, each has a relatively large number of fuel rods. It is composed of a large number of dispersed control rods that have a small neutron absorption effect, so it can flatten the power distribution of the reactor. This result shows that the fuel rods forming the aggregate
One or two types of UO 2 concentration is sufficient.
すなわち、解析によれば燃料集合体の断面を約
８cm×８cmとして、４×４又は５×５の正方格子
状に燃料棒を配するときは１種類の濃縮度のUO2
で十分である。又、５×５、６×６の正方格子状
に燃料棒を配するときは第３図に示すように各コ
ーナー部の２本又は３本の燃料棒のUO2濃度を他
の燃料棒のUO2濃度より下げることによつて良好
な出力分布が得られる。 In other words, according to the analysis, when the cross section of the fuel assembly is approximately 8 cm x 8 cm and the fuel rods are arranged in a 4 x 4 or 5 x 5 square grid, UO 2 of one type of enrichment is generated.
is sufficient. Also, when the fuel rods are arranged in a 5x5 or 6x6 square grid, the UO 2 concentration of two or three fuel rods at each corner is compared to that of the other fuel rods, as shown in Figure 3. Good output distribution can be obtained by lowering the UO 2 concentration.
第１図は従来の原子炉の説明図、第２図は本発
明の原子炉の一実施例を示す説明図、第３図は本
発明の他の実施例を示す説明図である。
１０…燃料集合体、２０…制御棒、３０…中性
子源又は中性子計装管。
FIG. 1 is an explanatory diagram of a conventional nuclear reactor, FIG. 2 is an explanatory diagram showing one embodiment of the nuclear reactor of the present invention, and FIG. 3 is an explanatory diagram showing another embodiment of the present invention. DESCRIPTION OF SYMBOLS 10... Fuel assembly, 20... Control rod, 30... Neutron source or neutron instrumentation tube.
Claims (1)
状に配し外周を八角形状のチヤンネルボツクスに
て囲繞して成る多数の燃料集合体を多数体配置さ
せ、この燃料集合体のコーナ部が相隣接して形成
する空所のすべてに制御棒、中性子計装系、中性
子源の内の１つを配置させ、前記制御棒は断面円
形の棒状制御棒でありかつ単独で上下動自在に支
持されて成ることを特徴とする沸騰水型原子炉。1 A large number of fuel assemblies are arranged in which a plurality of fuel rods are arranged in a square lattice shape except for the corner parts, and the outer periphery is surrounded by octagonal channel boxes, and the corner parts of the fuel assemblies are One of a control rod, a neutron instrumentation system, and a neutron source is arranged in all of the spaces formed adjacent to each other, and the control rod is a rod-shaped control rod with a circular cross section and is supported independently so as to be vertically movable. A boiling water nuclear reactor characterized by:
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP14385977A JPS5477892A (en) | 1977-12-02 | 1977-12-02 | Nuclear reactor |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP14385977A JPS5477892A (en) | 1977-12-02 | 1977-12-02 | Nuclear reactor |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS5477892A JPS5477892A (en) | 1979-06-21 |
| JPS6223273B2 true JPS6223273B2 (en) | 1987-05-22 |
Family
ID=15348623
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP14385977A Granted JPS5477892A (en) | 1977-12-02 | 1977-12-02 | Nuclear reactor |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS5477892A (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPH0424567U (en) * | 1990-06-25 | 1992-02-27 |
Citations (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS5094385A (en) * | 1973-12-20 | 1975-07-28 |
-
1977
- 1977-12-02 JP JP14385977A patent/JPS5477892A/en active Granted
Patent Citations (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS5094385A (en) * | 1973-12-20 | 1975-07-28 |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPH0424567U (en) * | 1990-06-25 | 1992-02-27 |
Also Published As
| Publication number | Publication date |
|---|---|
| JPS5477892A (en) | 1979-06-21 |
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