JPS6355495A - Core for nuclear reactor - Google Patents
Core for nuclear reactorInfo
- Publication number
- JPS6355495A JPS6355495A JP61198860A JP19886086A JPS6355495A JP S6355495 A JPS6355495 A JP S6355495A JP 61198860 A JP61198860 A JP 61198860A JP 19886086 A JP19886086 A JP 19886086A JP S6355495 A JPS6355495 A JP S6355495A
- Authority
- JP
- Japan
- Prior art keywords
- fuel
- core
- high conversion
- region
- orifice
- 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 claims description 58
- 230000000712 assembly Effects 0.000 claims description 7
- 238000000429 assembly Methods 0.000 claims description 7
- 238000006243 chemical reaction Methods 0.000 description 21
- 239000011800 void material Substances 0.000 description 11
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 8
- 230000000694 effects Effects 0.000 description 7
- 238000009835 boiling Methods 0.000 description 6
- 238000010586 diagram Methods 0.000 description 3
- 238000000034 method Methods 0.000 description 3
- 230000009257 reactivity Effects 0.000 description 3
- OYEHPCDNVJXUIW-FTXFMUIASA-N 239Pu Chemical compound [239Pu] OYEHPCDNVJXUIW-FTXFMUIASA-N 0.000 description 2
- UFHFLCQGNIYNRP-UHFFFAOYSA-N Hydrogen Chemical compound [H][H] UFHFLCQGNIYNRP-UHFFFAOYSA-N 0.000 description 1
- 239000002826 coolant Substances 0.000 description 1
- 239000000498 cooling water Substances 0.000 description 1
- 230000007423 decrease Effects 0.000 description 1
- 230000003247 decreasing effect Effects 0.000 description 1
- 229910052739 hydrogen Inorganic materials 0.000 description 1
- 239000001257 hydrogen Substances 0.000 description 1
- 239000003758 nuclear fuel Substances 0.000 description 1
- 239000012038 nucleophile Substances 0.000 description 1
- 238000012958 reprocessing Methods 0.000 description 1
- 125000006850 spacer group Chemical group 0.000 description 1
- JFALSRSLKYAFGM-UHFFFAOYSA-N uranium(0) Chemical compound [U] JFALSRSLKYAFGM-UHFFFAOYSA-N 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
- Organic Low-Molecular-Weight Compounds And Preparation Thereof (AREA)
- Placing Or Removing Of Piles Or Sheet Piles, Or Accessories Thereof (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) [Abstract] 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、軽水減速型原子炉に係り、特に、燃料棒密度
が異なる燃料集合体を炉心半径方向に配した沸騰水型原
子炉に関する。DETAILED DESCRIPTION OF THE INVENTION [Field of Industrial Application] The present invention relates to a light water-moderated nuclear reactor, and particularly to a boiling water reactor in which fuel assemblies having different fuel rod densities are arranged in the radial direction of the core.
核燃料の有効利用をはかる方法として、ワンススル一方
式がある。これは親核物質ウラン２３８からプルトニウ
ム２３９への転換を多くし、再処理をせずに続いてプル
トニウム２３９を焼す方法である。この例として、高転
換バーナ型炉心（特開昭６１−１２９５９４号公報）が
ある。この炉心は二種類の燃料集合体で構成されており
、各領域の水素原子数密度対燃料原子数密度比（以下Ｈ
／Ｕと記す）を変更している。One method for effectively utilizing nuclear fuel is the once-through method. This is a method that increases the conversion of the nucleophile uranium-238 to plutonium-239 and then burns the plutonium-239 without reprocessing. An example of this is a high conversion burner type core (Japanese Patent Application Laid-open No. 129594/1983). This core is composed of two types of fuel assemblies, and the ratio of hydrogen atomic number density to fuel atomic number density (hereinafter referred to as H
/U) has been changed.
高転換領域では中性子の平均エネルギを高くするためＨ
／Ｕを小さくする必要がある。このため、稠密格子燃料
を用いる。また、バーナ領域では逆にＨ／Ｕを大きくす
る必要があり、疎格子燃料を用いる。こ炉心では、現行
炉心と同様に燃料集合体入ロオリフ不スロ径として−様
な口径を用いて゛いる。沸騰水型高転換バーナ炉では二
つの領域の燃料格子間隔が異なるため、−様なオリフィ
ス口径の場合にも、稠密格子燃料は出力が高く沸騰によ
る気泡体積率（以下ボイド率とする）が疎格子燃料に比
べて高い。このため、Ｈ／Ｕは高転換領域で小さく、バ
ーナ領域で大きくなり各領域の特性が改善されている。In the high conversion region, H
/U needs to be made small. For this reason, dense lattice fuel is used. Moreover, in the burner region, it is necessary to increase H/U, and sparse lattice fuel is used. In this core, similar to the current core, various diameters are used as the diameters of the flow valves entering the fuel assemblies. In a boiling water type high conversion burner furnace, the fuel lattice spacing in the two regions is different, so even if the orifice diameter is -, dense lattice fuel has a high output and a low bubble volume ratio (hereinafter referred to as void ratio) due to boiling. Higher than lattice fuel. Therefore, H/U is small in the high conversion region and large in the burner region, improving the characteristics of each region.
従来技術における一様オリフイスを高転換バーナ炉に適
用した場合、稠密格子燃料があるため、炉心圧損が増大
するという問題があった。When the uniform orifice in the prior art is applied to a high conversion burner furnace, there is a problem in that the core pressure drop increases due to the presence of dense lattice fuel.
本発明の目的は、稠密格子燃料や疎格子燃料を並用した
多領域炉心から構成された沸騰水型高転換バーナ炉にお
いて、圧損を小さくする炉心を提供することにある。An object of the present invention is to provide a core that reduces pressure loss in a boiling water type high conversion burner furnace configured with a multi-zone core that uses both dense lattice fuel and sparse lattice fuel.
上記目的を達成すめため、本発明では燃料棒密度が高い
稠密格子燃料の入口オリフィス口径を、燃料棒密度が低
い疎格子燃料に比べて小さくしている。In order to achieve the above object, the present invention makes the inlet orifice diameter of a dense lattice fuel with a high fuel rod density smaller than that of a sparse lattice fuel with a low fuel rod density.
第７図に二つの領域のオリフィス口径を変えた場合の領
域間のボイド率差に対する圧損の変化を示す。高転換領
域の稠密格子燃料は燃料棒本数が多いため、一般に流路
面積が狭く出力が高い。逆に、バーナ領域の疎格子燃料
は燃料棒本数が少ないため、一般に流路面積が広く、出
力が低い。従つて、稠密格子燃料側は流動抵抗が大きい
ため、冷却水が入りにくく、容易に沸騰してボイド率が
高くなる。逆に、疎格子燃料はボイド率が低くなる。FIG. 7 shows the change in pressure drop with respect to the void ratio difference between the two regions when the orifice diameters of the two regions are changed. Dense lattice fuel in the high conversion region has a large number of fuel rods, so it generally has a narrow flow path area and high output. Conversely, sparse lattice fuel in the burner region has a small number of fuel rods, so generally has a wide flow path area and low output. Therefore, since the flow resistance is large on the dense lattice fuel side, it is difficult for cooling water to enter the fuel side, and it boils easily, resulting in a high void ratio. Conversely, sparse lattice fuel has a lower void fraction.
二つの領域のオリフィス口径を等しくした状態から高転
換領域のオリフィス口径を小さくし、バーナ領域のオリ
フィス口径を大きくした場合、第７図の矢印の方向に変
化し、二領域のボイド率の差が広がり、炉心の圧損が低
下する。If the orifice diameter in the high conversion region is made smaller and the orifice diameter in the burner region is increased from the state in which the orifice diameters of the two regions are made equal, the orifice diameter changes in the direction of the arrow in Fig. 7, and the difference in void ratio between the two regions increases. It spreads and the pressure drop in the core decreases.
このように稠密格子燃料を用いた高転換領域の入口オリ
フィス口径を小さくし、疎格子燃料を用いたバーナ領域
の入口オリフィス口径を大きくすることにより、全体の
圧損を低下させることができる。In this manner, by reducing the diameter of the inlet orifice in the high conversion region using dense lattice fuel and increasing the diameter of the inlet orifice in the burner region using sparse lattice fuel, the overall pressure drop can be reduced.
以下、本発明の詳細な説明する。 The present invention will be explained in detail below.
第１図は本発明の一実施例である炉心の概略横断面図で
ある。炉心中心領域１には稠密格子の燃料集合体６１Ａ
が配置されており、その周囲領域２には疎格子の燃料集
合体６１Ｂが配置されている。燃料集合体６１Ａ、６１
Ｂ内部には図中黒丸で示した位置にクラスタ型制御棒６
４が挿入できるようにシングル管５が置かれている。ま
た、疎格子燃料集合体６１Ｂには中性子の減速効果を良
くするために、内部に気泡を含まない水ロッド６が配置
されている。FIG. 1 is a schematic cross-sectional view of a core that is an embodiment of the present invention. A dense lattice fuel assembly 61A is located in the core center region 1.
is arranged, and in the surrounding area 2 a sparsely lattice fuel assembly 61B is arranged. Fuel assembly 61A, 61
Inside B, there is a cluster type control rod 6 at the position indicated by the black circle in the figure.
A single tube 5 is placed so that 4 can be inserted. Moreover, in order to improve the neutron moderating effect, water rods 6 that do not contain air bubbles are arranged inside the sparse lattice fuel assembly 61B.
燃料集合体６１Ａ及び６１Ｂの下端にオリフィス孔１２
を有するオリフィス板１４がそれぞれ取付けられている
。燃料集合体６１Ａに設けられたオリフィス板１４のオ
リフィス孔１２は、燃料集合体６１Ｂのそれに比べて小
さい。Orifice holes 12 are provided at the lower ends of the fuel assemblies 61A and 61B.
An orifice plate 14 having a diameter is attached to each of the orifice plates 14. The orifice hole 12 of the orifice plate 14 provided in the fuel assembly 61A is smaller than that in the fuel assembly 61B.
第２図ないし第４図に本発明で用いる燃料集合体の一実
施例を示す。燃料集合体は複数の燃料棒１５、下部タイ
プレート１６．上部タイプレート１７及びスペーサ１８
をもつ。２１は搬送用ハンドルである。下部タイプレー
ト１６及び上部タイプレート１７は、正六角形をしてい
る。燃料棒１５は、その両端が下部タイプレート１６及
び上部タイプレート１７にそれぞれ保持される。燃料棒
１５はチャンネルボックス２３内に正六角形になるよう
に配置されている。燃料棒１５のうち何本かはタイロッ
ド１５Ａであり、その両端は下部タイプレート１６及び
上部タイプレート１７に固定されている。An embodiment of the fuel assembly used in the present invention is shown in FIGS. 2 to 4. The fuel assembly includes a plurality of fuel rods 15, a lower tie plate 16. Upper tie plate 17 and spacer 18
have. 21 is a transportation handle. The lower tie plate 16 and the upper tie plate 17 have a regular hexagonal shape. The fuel rods 15 are held at both ends by a lower tie plate 16 and an upper tie plate 17, respectively. The fuel rods 15 are arranged in a regular hexagon in the channel box 23. Some of the fuel rods 15 are tie rods 15A, and both ends thereof are fixed to a lower tie plate 16 and an upper tie plate 17.
燃料集合体下端には、下部炉心支持板５６に挿入し、保
持するための円筒部１６Ａがあり、下部タイプレート１
６と放射状に配置された複数の連結板１６Ｂで結合され
ている。円筒部１６Ａの内部には、冷却材の流量を制御
するための入口オリフィス孔１２と制御棒が通るための
孔１３をもったオリフィス板１４が取付けられている。At the lower end of the fuel assembly, there is a cylindrical part 16A for inserting into and holding the lower core support plate 56, and the lower tie plate 1
6 and a plurality of connecting plates 16B arranged radially. An orifice plate 14 having an inlet orifice hole 12 for controlling the flow rate of the coolant and a hole 13 through which a control rod passes is mounted inside the cylindrical portion 16A.
第５図は本発明による炉心を用いたことによる効果を示
した図である。横軸に高転換領域のＨ／Ｕを縦軸に高転
換バーナ炉全体の中性子無限増倍率をとり、バーナ領域
のＨ／Ｕをパラメータとした時の関係を示している。高
転換領域のＨ／Ｕを小さくすると炉心全体の中性子無限
増倍率が増大して、炉心の反応度が高くなり、特性が改
善される０図中に示した矢印は、始点が二領域のボイド
率を等しくした時の状態で、終点が本発明によつて得ら
れた状態を示している。高転換領域のボイド率が増大し
Ｈ／ Ｕが小さくなったことにより、この効果が得られ
たものである。FIG. 5 is a diagram showing the effect of using the reactor core according to the present invention. The horizontal axis represents H/U in the high conversion region, the vertical axis represents the neutron infinite multiplication factor of the entire high conversion burner furnace, and the relationship is shown when H/U in the burner region is used as a parameter. When H/U in the high conversion region is reduced, the infinite neutron multiplication factor of the entire core increases, the reactivity of the core increases, and the characteristics are improved. The end point shows the state obtained by the present invention when the ratios are made equal. This effect was obtained by increasing the void ratio in the high conversion region and decreasing H/U.
第６図は本発明の他の実施例を示す炉心の横断面図であ
る。本実施例ではバーナ領域２で用いられている疎格子
燃料集合体６１Ｂでは水ロッド６が多数挿入されている
ため、流路面積は高転換領域１の燃料集合体６１Ａの流
路面積と等しい、これは水ロンドを増やすことにより、
Ｈ／Ｕを増やすように改良したものである。本実施例で
高転換領域のオリフィス口径を小さくし、バーナ領域の
オリフィス口径を大きくした場合には、バーナ領・域の
ボイド率が低くなるため、オリフィス口径を変えない場
合に比べてＨ／Ｕの改善効果が大きい。FIG. 6 is a cross-sectional view of a core showing another embodiment of the present invention. In this embodiment, since a large number of water rods 6 are inserted in the sparse grid fuel assembly 61B used in the burner region 2, the flow path area is equal to the flow path area of the fuel assembly 61A in the high conversion region 1. This is done by increasing water rondo.
This has been improved to increase H/U. In this example, if the orifice diameter in the high conversion region is made smaller and the orifice diameter in the burner region is increased, the void ratio in the burner region will be lower, so H/U will be lower than in the case where the orifice diameter is not changed. The improvement effect is large.
また、流量配分により、稠密格子燃料ではボイド率が高
くなるため、Ｈ／Ｕが低くなり、反応度を抑え、逆に疎
格子燃料ではボイド率が低くなるためＨ／ Ｕが高くな
り、反応度を増やして高燃焼度を達成することができ、
炉心の経済性を高めることができる。また、本発明によ
り沸騰水型高松換バーナ炉の高転換領域での高転換特性
、バーナ領域での高いバーナ効率を達成することができ
る。In addition, due to flow distribution, dense lattice fuel has a high void ratio, which lowers H/U and suppresses reactivity, whereas sparse lattice fuel has a low void ratio, which increases H/U and reduces reactivity. can achieve high burnup by increasing
The economic efficiency of the reactor core can be improved. Further, according to the present invention, it is possible to achieve high conversion characteristics in the high conversion region and high burner efficiency in the burner region of the boiling water type Takamatsu exchange burner furnace.
また、高転換バーナ炉の高転換領域ではボイド率が高く
なるため水力不安定が起こりやすいが、入口オリフィス
口径を小さくすることにより、単相流部の圧損を増やす
ことになり、水力安定性を高めることができる。In addition, hydraulic instability is likely to occur in the high conversion region of a high conversion burner furnace due to the high void ratio, but by reducing the inlet orifice diameter, the pressure drop in the single-phase flow section will increase, which will improve hydraulic stability. can be increased.
本発明によれば、燃料棒密度が異なる燃料集合体を用い
た沸騰水型高転換バーナ炉において、稠密格子燃料を用
いた場合にも、炉心圧損を増加させない様にすることが
できる。According to the present invention, in a boiling water type high conversion burner furnace using fuel assemblies with different fuel rod densities, it is possible to prevent core pressure loss from increasing even when dense lattice fuel is used.
第１図は本発明の一実施例の炉心の横断面図、第２図な
いし第４図は第１図の炉心で使用する燃料集合体の構造
図、第５図は本発明による効果の説明図、第６図は本発
明の他の実施例の炉心の横断面図、第７図は二領域の平
均ボイド率の差に対する炉心圧損の関係を示す特性図で
ある。
６１Ａ・・・稠密格子燃料集合体、６１Ｂ・・・疎格子
燃料集合体。FIG. 1 is a cross-sectional view of a core according to an embodiment of the present invention, FIGS. 2 to 4 are structural diagrams of fuel assemblies used in the core of FIG. 1, and FIG. 5 is an explanation of the effects of the present invention. 6 is a cross-sectional view of a core according to another embodiment of the present invention, and FIG. 7 is a characteristic diagram showing the relationship between the core pressure drop and the difference in average void fraction between two regions. 61A: dense lattice fuel assembly, 61B: sparse lattice fuel assembly.
Claims (1)
入れたものを燃料集合体とし、前記燃料棒の密度が異な
る前記燃料集合体を半径方向に配置した炉心において、 前記燃料棒の密度が大きい前記燃料集合体の入口オリフ
ィス口径を密度が小さい前記燃料集合体の前記入口オリ
フィス口径に比べて小さくしたことを特徴とする原子炉
の炉心。[Claims] 1. In a reactor core in which a plurality of fuel rods are bundled and placed in a cylindrical channel box as a fuel assembly, and the fuel assemblies having different fuel rod densities are arranged in the radial direction, A core for a nuclear reactor, characterized in that the diameter of the inlet orifice of the fuel assembly in which the density of the fuel rods is high is smaller than the diameter of the inlet orifice of the fuel assembly in which the density of the fuel rods is low.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP61198860A JPS6355495A (en) | 1986-08-27 | 1986-08-27 | Core for nuclear reactor |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP61198860A JPS6355495A (en) | 1986-08-27 | 1986-08-27 | Core for nuclear reactor |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPS6355495A true JPS6355495A (en) | 1988-03-09 |
Family
ID=16398122
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP61198860A Pending JPS6355495A (en) | 1986-08-27 | 1986-08-27 | Core for nuclear reactor |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS6355495A (en) |
-
1986
- 1986-08-27 JP JP61198860A patent/JPS6355495A/en active Pending
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