JPH0244288A - Fuel assembly for nuclear reactor - Google Patents
Fuel assembly for nuclear reactorInfo
- Publication number
- JPH0244288A JPH0244288A JP63193419A JP19341988A JPH0244288A JP H0244288 A JPH0244288 A JP H0244288A JP 63193419 A JP63193419 A JP 63193419A JP 19341988 A JP19341988 A JP 19341988A JP H0244288 A JPH0244288 A JP H0244288A
- Authority
- JP
- Japan
- Prior art keywords
- fuel
- fuel rods
- rods
- rod
- fuel assembly
- 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 title claims abstract description 104
- 229910052778 Plutonium Inorganic materials 0.000 claims description 6
- OYEHPCDNVJXUIW-UHFFFAOYSA-N plutonium atom Chemical compound [Pu] OYEHPCDNVJXUIW-UHFFFAOYSA-N 0.000 claims description 6
- 239000003758 nuclear fuel Substances 0.000 claims description 4
- 238000009826 distribution Methods 0.000 claims description 2
- 239000002574 poison Substances 0.000 claims description 2
- 231100000614 poison Toxicity 0.000 claims description 2
- 229910052770 Uranium Inorganic materials 0.000 abstract description 10
- JFALSRSLKYAFGM-UHFFFAOYSA-N uranium(0) Chemical compound [U] JFALSRSLKYAFGM-UHFFFAOYSA-N 0.000 abstract description 10
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 abstract description 10
- 230000009257 reactivity Effects 0.000 abstract description 6
- 238000010521 absorption reaction Methods 0.000 description 3
- 238000004519 manufacturing process Methods 0.000 description 3
- 238000012935 Averaging Methods 0.000 description 1
- 230000000712 assembly Effects 0.000 description 1
- 238000000429 assembly Methods 0.000 description 1
- 239000003795 chemical substances by application Substances 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 239000000835 fiber Substances 0.000 description 1
- 231100000086 high toxicity Toxicity 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)
Abstract
Description
【発明の詳細な説明】 ［発明の目的］ （産業上の利用分野） 本発明は原子炉用燃料集合体に関する。[Detailed description of the invention] [Purpose of the invention] (Industrial application field) The present invention relates to a fuel assembly for a nuclear reactor.
（従来の技術）
原子炉用燃料集合体において、各燃料棒の濃縮度おるい
はプルトニウム富化度を一様とすると局所的に（特に最
外周のコーナーにある燃料棒において）出力ピークが発
生して燃料の健全性を損なう可能性がある。そこで、従
来は第９図に示すように、数字１〜５で示すａ縮度タイ
プおるいはプルトニウム富化度タイプの異なる５種類の
燃料棒を組合わせて燃料集合体を構成して出力の平均化
を行い、これにより局所的出力ピーク値をできるだけ低
い値に押えてきた。なお、６は太径の水棒、７はチャン
ネルボックス、８は制御棒である。(Prior art) In a nuclear reactor fuel assembly, when the enrichment or plutonium enrichment of each fuel rod is made uniform, power peaks occur locally (especially in the fuel rods at the outermost corners). and may impair the integrity of the fuel. Therefore, conventionally, as shown in Figure 9, five types of fuel rods with different degrees of shrinkage or plutonium enrichment types, indicated by numbers 1 to 5, were combined to form a fuel assembly to increase output. Averaging was performed to suppress local output peak values to as low a value as possible. Note that 6 is a large diameter water rod, 7 is a channel box, and 8 is a control rod.
（発明が解決しようとする課題）
このような従来技術はタイプの異なる多数の燃料棒を用
いて燃料集合体を組立てるため製作コストが高くなる。(Problems to be Solved by the Invention) In this conventional technology, a fuel assembly is assembled using a large number of fuel rods of different types, resulting in high production costs.
またタイプの異なる多数の燃料棒を取扱うので、組立て
間違いを起こす可能性がめった。Also, since a large number of different types of fuel rods were handled, there was little chance of assembly errors.
ざらに、プルトニウムはその毒性が高いことから気密状
態で取扱う必要があり、異なるプルトニウム富化度を持
つ混合酸化物燃料棒（以下ＭＯＸと略す）を使うことは
燃料集合体の製作コス（・をざらに高めるという不具合
があった。Generally speaking, due to its high toxicity, plutonium must be handled in an airtight manner, and the use of mixed oxide fuel rods (hereinafter abbreviated as MOX) with different plutonium enrichments reduces the manufacturing cost of fuel assemblies. There was a problem that it increased too much.
本発明は上記事情に鑑みてなされたもので、その目的は
、少ない種類の燃料棒の組み合せで局所的出力ピークの
低い経済的な燃料集合体を提供することにおる。The present invention has been made in view of the above circumstances, and its purpose is to provide an economical fuel assembly with low local output peaks by combining a small number of types of fuel rods.
［発明の構成］
（課題を解決するための手段）
本発明は上記目的を達成するために、燃料濃縮度、プル
トニウム富化度おるいは可燃性毒物濃度の分布を有する
燃料棒を格子状に配列した原子炉用燃料集合体において
、混合酸化物燃料棒または高濃縮度燃料棒等の反応度の
高い燃料棒を燃料集合体の］−すを除く最外周に少なく
とも１本配置されていることを特徴とするものである。[Structure of the Invention] (Means for Solving the Problems) In order to achieve the above object, the present invention arranges fuel rods having a distribution of fuel enrichment, plutonium enrichment, or burnable poison concentration in a lattice pattern. In an arrayed nuclear reactor fuel assembly, at least one fuel rod with high reactivity, such as a mixed oxide fuel rod or a high enrichment fuel rod, is arranged on the outermost periphery of the fuel assembly excluding the -. It is characterized by:
（作 用）
本発明によれば、熱中性子吸収断面積の大きなＭＯＸ燃
料燃料撚料集合体の最外周に配置されているので、出力
ピークの出易いコーナの化ツクを相対的に下げることが
できる。(Function) According to the present invention, since the MOX fuel is disposed at the outermost periphery of the MOX fuel fiber assembly having a large thermal neutron absorption cross section, it is possible to relatively reduce the degree of distortion at corners where output peaks are likely to occur. can.
（実施例） 本発明の実施例を図を参照して説明する。(Example) Embodiments of the present invention will be described with reference to the drawings.
第１図は本発明の一実施例の横断面図であり、同図に示
すように、燃料集合体は１本の大径ウォーターロッド１
３を中央部に配置し、格子状に配置された燃料棒の最外
周の各辺の中央に２本のＭＯ×燃料燃料２を、またそれ
以外の最外周の各辺の個所にはウラン燃料＋！１１を配
置し、その伯の部分にはＭＯＸ燃料棒１２を配置したも
ので、全体として８（１８列の正方格子状に構成されて
いる。１０はチャンネルボックス、１４は制御棒でおる
。FIG. 1 is a cross-sectional view of one embodiment of the present invention, and as shown in the figure, the fuel assembly consists of one large-diameter water rod 1.
3 is placed in the center, two MO x fuel 2 are placed in the center of each side of the outermost periphery of the fuel rods arranged in a lattice pattern, and uranium fuel is placed in the other places on each side of the outermost periphery. +! 11 are arranged, and MOX fuel rods 12 are arranged in the squared part, and the whole is configured in a square lattice shape of 8 (18 rows). 10 is a channel box, and 14 is a control rod.
次に、本実施例の作用について説明する。Next, the operation of this embodiment will be explained.
第２図は最外周の反応度の高い燃料棒の装荷割合と局所
出力ビーキング係数との関係を示したものであり、装荷
割合が１．０となったところが最外周のコーナに反応度
の高い燃料棒を配置した場合を示している。同図より明
らかなように、反応度の高い燃料棒を燃料集合体のコー
ナを除く最外周に少なくとも１本配置することにより、
局所出力ピークを１０％下げることができる。Figure 2 shows the relationship between the loading ratio of fuel rods with high reactivity on the outermost periphery and the local power peaking coefficient, and the loading ratio of 1.0 indicates the high reactivity on the outermost corner. This shows the arrangement of fuel rods. As is clear from the figure, by arranging at least one fuel rod with high reactivity on the outermost periphery of the fuel assembly excluding the corners,
Local power peaks can be reduced by 10%.
本発明のように最外周にＭＯＸ燃料棒１２を配置すると
、ＭＯＸ燃料燃料２のもつ大きな吸収断面積により、出
力ピークの出易いコーナの出力を押えることができる。When the MOX fuel rods 12 are arranged at the outermost periphery as in the present invention, the large absorption cross-sectional area of the MOX fuel 2 makes it possible to suppress the output at corners where output peaks are likely to occur.
第３図は本発明の第２の実施例の横断面図でおり、燃料
集合体は１木の大径ウォーターロッド１３を中央部に配
置し、最外周各辺のみの中央部に４木のＭＯＸ燃料棒１
２を、またそれ以外の最外周の各辺の個所にはウラン燃
料棒１１を配置し、さらに最外周の各辺から内側にはＭ
ＯＸ燃料燃料２を配置したもので、全体として８行８列
の正方格子状に構成したものである。FIG. 3 is a cross-sectional view of the second embodiment of the present invention, in which the fuel assembly has one large-diameter water rod 13 arranged in the center, and four water rods in the center only on each side of the outermost periphery. MOX fuel rod 1
2, and uranium fuel rods 11 are arranged on each side of the other outermost periphery, and M
The OX fuel 2 is arranged in a square lattice with 8 rows and 8 columns as a whole.
第４図は本発明の第３の実施例の横断面図であり、燃料
集合体は１本の大径ウォーターロッド１３を中央部に配
置し、また最外周のコーナにのみウラン燃料棒１１とし
、それ以外はすべてＭＯＸ燃料棒１２としたもので、全
体として８行８列の正方格子状に構成したものである。FIG. 4 is a cross-sectional view of a third embodiment of the present invention, in which the fuel assembly has one large-diameter water rod 13 disposed in the center, and uranium fuel rods 11 only at the outermost corners. , all other fuel rods are MOX fuel rods 12, and the entire structure is arranged in a square lattice of 8 rows and 8 columns.
上述したように第１図の第１の実施例では最外周の各辺
に２本ずつ反応度の高い燃料棒をおいた場合を示したが
、第３図の第２の実施例及び第４図の第３の実施例のよ
うに燃料の対称性を考慮して、４本ないし６本を配置す
ることもできる。As mentioned above, the first embodiment shown in FIG. 1 shows the case where two fuel rods with high reactivity are placed on each side of the outermost periphery, but the second embodiment and the fourth embodiment shown in FIG. Considering the symmetry of the fuel, it is also possible to arrange four to six fuels as in the third embodiment shown in the figure.
上記した各実施例は燃料棒が８行８列の正方格子状に配
列されている燃料集合体について）ホべたが、本発明は
以下で説明する第４実施例〜第７実施例のように燃料棒
が９行９列の正方格子状に配列されている燃料集合体に
ついても適用できる。Each of the above-mentioned embodiments has been described with respect to a fuel assembly in which fuel rods are arranged in a square grid of 8 rows and 8 columns, but the present invention is based on the fourth to seventh embodiments described below. The present invention can also be applied to a fuel assembly in which fuel rods are arranged in a square lattice of 9 rows and 9 columns.
第５図は本発明の第４の実施例の横断面図であり、燃料
集合体は１本の大径ウォーターロッド１８を中央部に配
置し、また最外周に配置の燃料棒はその中央の燃料棒の
みをＭＯＸ燃料４４１７とし、その他はウラン燃料棒１
６とする。ざらに最外周から第２番目のコーナの燃料棒
のみをウラン燃（゛４棒１６としその使の燃料棒はすべ
てＭＯＸ燃料棒１７とし、全体として９行９列の正方格
子状に構成したものである。１５はチャンネルボックス
である。FIG. 5 is a cross-sectional view of a fourth embodiment of the present invention, in which the fuel assembly has one large diameter water rod 18 disposed in the center, and the fuel rods disposed at the outermost periphery are located in the center. Only the fuel rods are MOX fuel 4417, the rest are uranium fuel rods 1
Set it to 6. Roughly speaking, only the fuel rods at the second corner from the outermost periphery are uranium-fueled (4 rods 16, and all of the fuel rods in use are MOX fuel rods 17, and the overall configuration is in a square lattice of 9 rows and 9 columns. 15 is a channel box.
第６図は本発明の第５の実施例の横断面図であり、燃料
集合体は１本の大径ウォーターロッド１８を中央部に配
置し、また最外周に配置の燃料棒はその中央部の３本の
燃料棒をＭＯＸ燃料棒１７とし、その他にウラン燃料棒
１６とする。さらに最外周から第２番目のコーナの燃料
棒のみをウラン燃料棒１６とし、その他の燃料棒はすべ
てＭＯＸ燃料棒１７とし、全体として９行９列の正方格
子状に構成したものである。FIG. 6 is a cross-sectional view of a fifth embodiment of the present invention, in which a fuel assembly has one large-diameter water rod 18 arranged in the center, and the fuel rods arranged at the outermost periphery are arranged in the center. The three fuel rods are assumed to be MOX fuel rods 17, and the others are assumed to be uranium fuel rods 16. Further, only the fuel rods at the second corner from the outermost periphery are uranium fuel rods 16, and all other fuel rods are MOX fuel rods 17, and the overall configuration is in the form of a square lattice with 9 rows and 9 columns.
第７図は本発明の第６の実施例の横断面図であり、燃料
集合体は１本の大径ウォーターロッド１８を中央部に配
置し、また最外周に配置の燃料棒はそのコーナの燃料棒
とそれに隣接する燃料棒をウラン燃料棒１６とし、その
他の燃料棒をすべてＭＯ×燃料燃料７とし、全体として
９行９列の正方格子状に構成したものである。FIG. 7 is a cross-sectional view of a sixth embodiment of the present invention, in which the fuel assembly has one large diameter water rod 18 disposed in the center, and the fuel rods disposed at the outermost periphery are located at the corners. The fuel rods and the fuel rods adjacent thereto are uranium fuel rods 16, and all other fuel rods are MO×fuel 7, and the overall configuration is a square lattice of 9 rows and 9 columns.
第８図は本発明の第７の実施例の横断面図であり、燃料
集合体は１本の太径つを一ターロッド１８を中央部に配
置し、また最外周のコーナにのみウラン燃料棒１６とし
、その他の燃料棒はすべてＭＯＸ燃利燃料７とし、全体
として９行９列の正方格子状に構成したものでおる。FIG. 8 is a cross-sectional view of a seventh embodiment of the present invention, in which the fuel assembly has one large-diameter rod and a tar rod 18 disposed in the center, and uranium fuel rods are located only at the outermost corners. 16, and all other fuel rods are MOX fuel 7, and the overall structure is a square lattice of 9 rows and 9 columns.
［発明の効果］
以上説明したように、本発明によれば、熱中性子吸収断
面積の大きなＭＯＸ燃料棒が燃料集合体の最外周に配置
されているので、出力ピークの出易いコーナの出力を相
対的に下げることができる。[Effects of the Invention] As explained above, according to the present invention, since the MOX fuel rods with a large thermal neutron absorption cross section are arranged at the outermost periphery of the fuel assembly, the output at corners where output peaks are likely to occur can be reduced. It can be lowered relatively.
したがって、従来のようにタイプの異なる多種類の燃料
棒を用いずに、少ない種類の燃料棒で局所出力ピークの
十分に低くかつ製造コス（〜の低い原子炉用燃料集合体
を提供することができる。Therefore, it is possible to provide a nuclear reactor fuel assembly with sufficiently low local power peaks and low manufacturing costs (~) using a small number of fuel rods, without using many different types of fuel rods as in the past. can.
第１図は本発明の一実施例の横断面図、第２図は最外周
の反応度の高い燃料棒の装荷割合と局所出力ビーキング
係数との関係を示した図、第３図〜第８図はいずれも本
発明の第２〜第７実施例の横断面図、第９図は従来の燃
料集合体の横断面図である。
１０、１５・・・チャンネルボックス
１１、１６・・・ウラン燃料棒
１２、１７・・・ＭＯＸ燃料棒
１３、１８・・・大径ウォーターロッド１４・・・制御
棒
（８７３３）代理人 弁理士 猪 股 祥 晃（ばか
１名）
００ α２５０．りρ １２７Ｓ ｒ、θ桑外高４
−１シυυた料琴荷↑今
第２図
第１図
第３図
第
図
第
図
第
図
第
図FIG. 1 is a cross-sectional view of an embodiment of the present invention, FIG. 2 is a diagram showing the relationship between the loading ratio of highly reactive fuel rods on the outermost periphery and the local power peaking coefficient, and FIGS. 3 to 8 Each figure is a cross-sectional view of second to seventh embodiments of the present invention, and FIG. 9 is a cross-sectional view of a conventional fuel assembly. 10, 15...Channel box 11, 16...Uranium fuel rod 12, 17...MOX fuel rod 13, 18...Large diameter water rod 14...Control rod (8733) Agent Patent attorney Boar Yoshiaki Mata (baka)
1 person) 00 α250. riρ 127S r, θ Kuwagai height 4
-1shi υυ charge ↑ Now Figure 2 Figure 1 Figure 3 Figure 3 Figure Figure Figure Figure
Claims (1)
毒物濃度の分布を有する燃料棒を格子状に配列した原子
炉用燃料集合体において、混合酸化物燃料棒または高濃
縮度燃料棒等の反応度の高い燃料棒を燃料集合体のコー
ナを除く最外周に少なくとも１本配置されていることを
特徴とする原子炉用燃料集合体。(1) In a nuclear reactor fuel assembly in which fuel rods with distributions of fuel enrichment, plutonium enrichment, or burnable poison concentration are arranged in a lattice, the reaction of mixed oxide fuel rods or high enrichment fuel rods, etc. A fuel assembly for a nuclear reactor, characterized in that at least one high-strength fuel rod is arranged on the outermost periphery of the fuel assembly excluding corners.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP63193419A JPH0244288A (en) | 1988-08-04 | 1988-08-04 | Fuel assembly for nuclear reactor |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP63193419A JPH0244288A (en) | 1988-08-04 | 1988-08-04 | Fuel assembly for nuclear reactor |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPH0244288A true JPH0244288A (en) | 1990-02-14 |
Family
ID=16307653
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP63193419A Pending JPH0244288A (en) | 1988-08-04 | 1988-08-04 | Fuel assembly for nuclear reactor |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH0244288A (en) |
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| WO1993004479A1 (en) * | 1990-02-26 | 1993-03-04 | Kabushiki Kaisha Toshiba | Fuel assembly for thermal reactor |
| US6658078B2 (en) * | 2001-07-23 | 2003-12-02 | Tokyo Electric Power Co. | MOX nuclear fuel assembly employable for a thermal neutron nuclear reactor |
-
1988
- 1988-08-04 JP JP63193419A patent/JPH0244288A/en active Pending
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| WO1993004479A1 (en) * | 1990-02-26 | 1993-03-04 | Kabushiki Kaisha Toshiba | Fuel assembly for thermal reactor |
| US6658078B2 (en) * | 2001-07-23 | 2003-12-02 | Tokyo Electric Power Co. | MOX nuclear fuel assembly employable for a thermal neutron nuclear reactor |
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