JPH0363714B2 - - Google Patents
Info
- Publication number
- JPH0363714B2 JPH0363714B2 JP58163123A JP16312383A JPH0363714B2 JP H0363714 B2 JPH0363714 B2 JP H0363714B2 JP 58163123 A JP58163123 A JP 58163123A JP 16312383 A JP16312383 A JP 16312383A JP H0363714 B2 JPH0363714 B2 JP H0363714B2
- Authority
- JP
- Japan
- Prior art keywords
- fuel
- fast breeder
- breeder reactor
- opening
- fuel assemblies
- 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 - Lifetime
Links
- 239000000446 fuel Substances 0.000 claims description 31
- 230000000712 assembly Effects 0.000 claims description 13
- 238000000429 assembly Methods 0.000 claims description 13
- 239000007788 liquid Substances 0.000 claims description 3
- 239000002826 coolant Substances 0.000 description 8
- 238000001816 cooling Methods 0.000 description 3
- 230000009291 secondary effect Effects 0.000 description 2
- 238000002485 combustion reaction Methods 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 230000003993 interaction Effects 0.000 description 1
- 230000008961 swelling 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
- Heat-Exchange Devices With Radiators And Conduit Assemblies (AREA)
Description
【発明の詳細な説明】
〔発明の利用分野〕
本発明は高速増殖炉に係り、特に炉心部の冷却
に対する好適な炉心構造に関するものである。DETAILED DESCRIPTION OF THE INVENTION [Field of Application of the Invention] The present invention relates to a fast breeder reactor, and particularly to a core structure suitable for cooling the reactor core.
第１図に燃料集合体の概念を示す。各燃料要素
１は束ねられ、ラツパ管２に収容納れる。ラツパ
管２には臨接する燃料集合体との機械的相互作用
に耐え得る様にパツド３が設けられ、ラツパ管２
を補強している。冷却材はエントランスノズル４
のオリフイス孔５から流入し、ハンドリングヘツ
ド６側から流出する。燃料要素は束は極めて密に
配列されるため流速が６ｍ／sec以上となり、大
きな圧力損失（４Kg／cm2）が発生し、原子炉冷却
系の圧力損失の内、５割から８割を占めることと
なつている。また径方向非均質炉心の様な隣り合
う燃料集合体として燃焼初期に発熱の少ないブラ
ンケツト燃料集合体が配された場合、あるいは、
均質炉心においても燃料集合体と隣り合つて制御
棒が配される場合等、冷却材出口温度が隣り同志
で大きく異なることがあり、炉心上部機構に熱疲
労を与え、き裂の発生し易い条件となつている。
Figure 1 shows the concept of a fuel assembly. Each fuel element 1 is bundled and housed in a wrapper tube 2. The wrapper tube 2 is provided with a pad 3 so as to withstand mechanical interaction with the adjoining fuel assembly.
is reinforced. Coolant is at entrance nozzle 4
It flows in from the orifice hole 5 and flows out from the handling head 6 side. Because the fuel element bundles are arranged extremely densely, the flow velocity is over 6 m/sec, which causes a large pressure loss (4 kg/cm 2 ), which accounts for 50% to 80% of the pressure loss in the reactor cooling system. It has become commonplace. In addition, when blanket fuel assemblies that generate less heat at the beginning of combustion are arranged as adjacent fuel assemblies such as in a radially non-homogeneous core, or
Even in a homogeneous core, when control rods are placed next to fuel assemblies, the coolant outlet temperature may vary greatly between adjacent ones, causing thermal fatigue to the upper core mechanism and creating conditions that make cracks more likely to occur. It is becoming.
本発明の目的は、圧力損失が小さく、かつ燃料
集合体の出口温度差の小さな炉心構造を提供する
ものである。
An object of the present invention is to provide a reactor core structure with small pressure loss and a small difference in outlet temperature of fuel assemblies.
本発明は、ラツパ管２に設けられたパツト部３
に開孔部を設け、ここからの冷却材流出によつて
燃料要素束部の流速を下げ、圧力損失を低減する
ものである。また、この開孔部を通した隣り合う
燃料集合体同志のミキシングにより、出口温度差
を低減するものである。
The present invention provides a patch portion 3 provided in a wrapper tube 2.
An opening is provided in the fuel element, through which the coolant flows out, thereby lowering the flow velocity of the fuel element bundle and reducing pressure loss. Further, by mixing adjacent fuel assemblies through this opening, the difference in outlet temperature is reduced.
燃料要素１は第２図に示す発熱する炉心燃料部
７とその上下のブランケツト燃料部８、さらにガ
スプレナム部９から構成され、ガスプレナム部９
の長さは全長の約４割を占めている。ラツパ管２
に設けられたパツド３の軸方向位置は第２図の横
に示す如く上部ブランケツト部の上端付近であ
る。これは中性子照射によるスエリングを逃れる
ため、炉中心を外して設定されているためであ
る。冷却材は炉心部７を通り抜けた後は、ほとん
ど加熱を受ける事がないため、ラツパ管に開孔部
を設けて冷却材を逃すことができる。この場合は
そこからの冷却材流出分だけ流速が減り、圧力損
失が低減される。しかしながらラツパ管２は中性
子経済性を高めるため限界まで薄肉化されてお
り、開孔部を設ける事による応力の増大を許容す
る事ができない。第３図は本発明の一実施例を示
すもので、パツド部３に開孔部１０を設けたもの
である。本開孔部１０の設置によつて燃料集合体
内を流れる冷却材流量は約30％低減し、これによ
る圧力損失は流速の２乗に比例するため単位長さ
あたり約50％低減され、結果として集合体全体と
しての圧力損失は3.2Kg／cm2と約20％低減される。
また隣り合う燃料集合体間でこの開孔部１０を介
したミキシングによつて出口部の冷却材温度差は
約20％低減し、熱サイクル疲労寿命を約５倍とす
る事ができる。第４図は本発明の別の実施例を示
したもので、パツド部３に設けられた開孔部１０
に溝１１を設けたもので、均質炉心の様な隣り合
う燃料集合体同志の温度差が小さい場合のための
ものであり、ミキシングよりも、開孔部１０から
の流出量増大を主眼としたものである。この場合
には燃料集合体全体の圧力損失は約25％低減す
る。
The fuel element 1 is composed of a heat generating core fuel section 7 shown in FIG. 2, blanket fuel sections 8 above and below it, and a gas plenum section 9.
occupies about 40% of the total length. Ratsupa pipe 2
The axial position of the pad 3 is near the upper end of the upper blanket portion, as shown on the side in FIG. This is because the reactor is set away from the center to avoid swelling caused by neutron irradiation. Since the coolant is hardly heated after passing through the reactor core 7, an opening can be provided in the wrapper tube to allow the coolant to escape. In this case, the flow velocity is reduced by the amount of coolant flowing out from there, and pressure loss is reduced. However, the Lamp tube 2 has been made as thin as possible in order to improve neutron economy, and cannot tolerate an increase in stress due to the provision of openings. FIG. 3 shows an embodiment of the present invention, in which a hole 10 is provided in the pad portion 3. As shown in FIG. By installing this opening 10, the flow rate of coolant flowing inside the fuel assembly is reduced by about 30%, and the resulting pressure loss is proportional to the square of the flow velocity, so it is reduced by about 50% per unit length. The pressure loss of the entire assembly is reduced by approximately 20% to 3.2Kg/cm 2 .
Also, by mixing between adjacent fuel assemblies through the apertures 10, the temperature difference of the coolant at the outlet can be reduced by about 20%, and the thermal cycle fatigue life can be increased by about 5 times. FIG. 4 shows another embodiment of the present invention, in which an opening 10 provided in the pad portion 3 is shown.
This is for cases where the temperature difference between adjacent fuel assemblies is small, such as in a homogeneous core, and the main purpose is to increase the amount of outflow from the openings 10 rather than mixing. It is something. In this case, the pressure loss across the fuel assembly is reduced by approximately 25%.
一方隣り合う燃料集合体同志の温度差が極めて
大きい場合、ミキシングを行なわせる事により燃
料集合体内部での熱疲労が大きくなり、問題の生
ずる様な場合があり、この様な場合には燃料集合
体の六面全てに開孔部を設ける事をせず、隣接す
る燃料集合体同志互に対面しない開孔とする事も
可能である。 On the other hand, if the temperature difference between adjacent fuel assemblies is extremely large, mixing may increase thermal fatigue inside the fuel assemblies, causing problems. It is also possible not to provide openings on all six sides of the body, but to provide openings that do not face adjacent fuel assemblies.
以上述べた実施例を採用する事によつて次に述
べる様な副次的効果も得られる。すなわち、燃料
交換に際して引抜かれた燃料の崩壊熱を除去する
ため自然循環冷却能力が要求されるが、パツド部
３に開孔部１０を持たない場合は第５図ａに示す
様に液面はハンドリングヘツド６よりも上になけ
ればならない。開孔部１０を設けることにより、
液面は第５図ｂに示す様に引下げる事が可能とな
り、原子炉容器の高さを低くでき、コンパクト化
によるコストの低減が計れるものである。 By employing the embodiments described above, the following secondary effects can also be obtained. In other words, natural circulation cooling capacity is required to remove the decay heat of the extracted fuel during fuel exchange, but if the pad part 3 does not have the opening 10, the liquid level will decrease as shown in Figure 5a. It must be above the handling head 6. By providing the opening 10,
The liquid level can be lowered as shown in Figure 5b, allowing the height of the reactor vessel to be lowered and cost reduction due to compactness.
以上述べた様に、本発明によれば圧力損失が低
減され、また燃料集合体間の出入口温度差の小さ
な高速増殖炉を提供でき、更に原子炉容器の小型
化も計る事ができる。
As described above, according to the present invention, it is possible to provide a fast breeder reactor with reduced pressure loss and a small difference in entrance and exit temperatures between fuel assemblies, and it is also possible to reduce the size of the reactor vessel.
第１図は燃料集合体の構造を示す半断面図、第
２図は燃料要素の構造とラツパ管パツド部の軸方
向位置を説明するための半断面図、第３図は本発
明の実施例を示す側面図、第４図は本発明の他の
実施例を示す側面図、第５図は本発明による副次
的効果を示す側面図である。
２……ラツパ管、３……パツド、１０……開孔
部、１１……溝。
Fig. 1 is a half-sectional view showing the structure of the fuel assembly, Fig. 2 is a half-sectional view illustrating the structure of the fuel element and the axial position of the wrapper tube pad, and Fig. 3 is an embodiment of the present invention. FIG. 4 is a side view showing another embodiment of the present invention, and FIG. 5 is a side view showing secondary effects of the present invention. 2...Ratsupa tube, 3...Pud, 10...Opening part, 11...Groove.
Claims (1)
の存在範囲よりも上側のラツパ管部に設けられた
パツドに開孔部を設けたことを特徴とする高速増
殖炉。 ２ 特許請求の範囲第１項において、パツド部に
設けられた開孔部は隣接する燃料集合体同志互に
対面した開孔となつていることを特徴とする高速
増殖炉。 ３ 特許請求の範囲第１項において、パツド部に
設けられた開孔部は隣接する燃料集合体同志互に
対面しない開孔となつていることを特徴とする高
速増殖炉。 ４ 特許請求の範囲第２項において、開孔部には
溝を設けることを特徴とする高速増殖炉。 ５ 特許請求の範囲第１項において、燃料交換時
の液面を引抜かれた燃料集合体の開孔部高さとす
ることを特徴とする高速増殖炉。[Scope of Claims] 1. A fast breeder reactor characterized in that, in a fuel assembly for a fast breeder reactor, an opening is provided in a pad provided in a wrapper tube section above an area where core fuel exists. 2. The fast breeder reactor according to claim 1, characterized in that the openings provided in the pad portion are openings that face adjacent fuel assemblies. 3. A fast breeder reactor according to claim 1, characterized in that the openings provided in the pad portion do not face adjacent fuel assemblies. 4. The fast breeder reactor according to claim 2, characterized in that a groove is provided in the opening. 5. A fast breeder reactor according to claim 1, characterized in that the liquid level at the time of refueling is set to the height of the opening of the pulled fuel assembly.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP58163123A JPS6055288A (en) | 1983-09-07 | 1983-09-07 | fast breeder reactor |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP58163123A JPS6055288A (en) | 1983-09-07 | 1983-09-07 | fast breeder reactor |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS6055288A JPS6055288A (en) | 1985-03-30 |
| JPH0363714B2 true JPH0363714B2 (en) | 1991-10-02 |
Family
ID=15767615
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP58163123A Granted JPS6055288A (en) | 1983-09-07 | 1983-09-07 | fast breeder reactor |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS6055288A (en) |
Families Citing this family (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2525827B2 (en) * | 1987-09-07 | 1996-08-21 | 株式会社東芝 | Fuel assembly |
| JP6219752B2 (en) * | 2014-03-04 | 2017-10-25 | 日立Ｇｅニュークリア・エナジー株式会社 | Fast reactor core |
-
1983
- 1983-09-07 JP JP58163123A patent/JPS6055288A/en active Granted
Also Published As
| Publication number | Publication date |
|---|---|
| JPS6055288A (en) | 1985-03-30 |
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