JPS60171494A - Method of charging fuel - Google Patents
Method of charging fuelInfo
- Publication number
- JPS60171494A JPS60171494A JP59027105A JP2710584A JPS60171494A JP S60171494 A JPS60171494 A JP S60171494A JP 59027105 A JP59027105 A JP 59027105A JP 2710584 A JP2710584 A JP 2710584A JP S60171494 A JPS60171494 A JP S60171494A
- Authority
- JP
- Japan
- Prior art keywords
- fuel
- fuel assembly
- special
- core
- pattern
- 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
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
- Jet Pumps And Other Pumps (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】
〔発明の利用分野〕
本発明は1/4炉心回転対称燃料交換パターン採用時の
圧力管型原子炉に係り、その燃料装荷方法に関する。DETAILED DESCRIPTION OF THE INVENTION [Field of Application of the Invention] The present invention relates to a pressure tube nuclear reactor when a 1/4 core rotationally symmetric fuel exchange pattern is adopted, and to a fuel loading method therefor.
1/4炉心回転対称燃料交換パターン採用時には周期的
に新燃料が炉心に集まるため、炉中心の燃料集合体を他
の燃料と同一とした場合には、第5図に示すように周期
的に大きな出力ビーキングが炉中心に発生し、最大線出
力密度が制限値を超える。When a 1/4 core rotationally symmetrical refueling pattern is adopted, new fuel collects in the core periodically, so if the fuel assembly at the center of the reactor is the same as other fuels, it will be collected periodically as shown in Figure 5. A large power peaking occurs at the center of the furnace, and the maximum linear power density exceeds the limit value.
(1)
上記出力ビーキングを抑制するため、出力平坦化用制御
棒の使用も考えられるが、制御棒使用により、軸方向出
力分布が大きな下ぶくれとなり歪むほか、挿入した制御
棒を一定期間経過した後、引抜いた時には、制御棒挿入
のため、これまで燃焼が進んでいない燃料の熱発生が急
激に加わるため、出力ビーキングは改善されない。(1) In order to suppress the above-mentioned output peaking, it is possible to use control rods for output flattening. When the control rods are inserted and the control rods are inserted, heat generation from the fuel, which has not yet been combusted, is rapidly added, so power peaking is not improved.
一方、この出力ビーキングの抑制のため、制御棒をサイ
クル途中で引き抜くことなく、サイクル末期まで使用す
ると、燃焼度の損失を招くことになる。On the other hand, if the control rods are used until the end of the cycle without being withdrawn in the middle of the cycle in order to suppress this power peaking, a loss in burnup will result.
以上の結果を踏まえ、従来例では、第1図、第2図に示
すように、燃料交換パターンとしては全炉心一様分散燃
料交換パターンを採用している。Based on the above results, in the conventional example, as shown in FIGS. 1 and 2, the entire core uniformly distributed fuel exchange pattern is adopted as the fuel exchange pattern.
このため、新燃料が周期的に集中することがなくなり、
出力ビーキングは改善された。しかしながら、全炉心一
様分散燃料交換パターン採用により、各領域(象限毎)
の領域出力が異なってしまい、領域間で出力のアンバラ
ンスが生じている。This eliminates the periodic concentration of new fuel.
Output beaking has been improved. However, by adopting a uniform distributed refueling pattern for the whole core, each region (quadrant by quadrant)
The area outputs of the two areas differ, causing an output imbalance between the areas.
(2)
本発明の目的は、上記欠点を取り除き、1/4炉心回転
対称燃料交換方式を制御棒を使用する事なく実現しうる
圧力管型原子炉の燃料装荷法を提供することにある。(2) An object of the present invention is to provide a fuel loading method for a pressure tube nuclear reactor that eliminates the above-mentioned drawbacks and allows a 1/4 core rotationally symmetric fuel exchange system to be realized without using control rods.
1/4炉心回転対称燃料交換パターンを採用した場合、
周期的に炉中心部4体が同一時期に新燃料となり、出力
ビーキングが増大するのを防止するため、この位置に、
他の燃料集合体よりも濃縮度の低い燃料を装荷する。こ
の際、濃縮度の低い燃料を新たに使用すると燃料のコス
ト上昇を招くので、この位置に特殊燃料集合体を装荷す
る。特殊燃料集合体の濃縮度としては出力ビーキングを
制限値内に抑えうる濃縮度まで低下するが、このように
しても、特殊燃料集合体内の圧力管部材照射試験片の高
速中性子照射積算量は制限値を満足する。If a 1/4 core rotationally symmetric fuel exchange pattern is adopted,
In order to prevent the four bodies in the core of the reactor from periodically receiving new fuel at the same time and increasing the output peaking, a
Load fuel with lower enrichment than other fuel assemblies. At this time, since newly using fuel with a low enrichment level will increase the cost of the fuel, a special fuel assembly is loaded at this position. The enrichment of the special fuel assembly will be reduced to an enrichment level that can suppress output peaking within the limit value, but even with this, the cumulative amount of fast neutron irradiation of the irradiated test piece of the pressure pipe member in the special fuel assembly will be limited. satisfy the value.
〔発明の実施例〕 本発明の実施例を第3図、第4図に示す。[Embodiments of the invention] Examples of the present invention are shown in FIGS. 3 and 4.
燃料交換パターンとして第4図に示す1/4炉(3)
心回転対称燃料交換パターンを採用する。また、燃料交
換は標準燃料集合体1については各サイクルで全体の1
74を交換する4バツチ燃料交換とする。すなわち、第
4図において、各燃料集合体の番号は同時期に交換する
燃料集合体lを示し、番号の小さい順から順次交換して
ゆく。As the fuel exchange pattern, the 1/4 reactor (3) rotationally symmetrical fuel exchange pattern shown in Figure 4 will be adopted. In addition, for standard fuel assembly 1, fuel exchange is performed for the entire 1 in each cycle.
74 will be replaced in 4 batches. That is, in FIG. 4, the number of each fuel assembly indicates the fuel assembly l to be replaced at the same time, and the fuel assemblies 1 are replaced in order from the smallest number.
一方、特殊燃料集合体2は炉心中心部に装荷し、燃料交
換は特殊燃料集合体に対する最高燃焼度の制限から2バ
ツチ燃料交換とする。On the other hand, the special fuel assembly 2 is loaded in the center of the core, and the fuel exchange is performed in two batches due to the maximum burnup limit for the special fuel assembly.
特殊燃料集合体2を1/4炉心回転対称燃料交換パター
ンの中心に装荷することにより、周期的に大きな出力ビ
ーキングが発生し、従来例と同一の濃縮度の特殊燃料集
合体を装荷すると、最大線出力密度が制限値を超えるが
、逆に言うと、濃縮度を低下させた特殊燃料集合体2の
採用で従来と同程度の特殊°燃料集合体2の出力ビーキ
ングが得られ、照射試験片の高速中性子照射積算量を確
保できる。By loading the special fuel assembly 2 at the center of the 1/4 core rotationally symmetrical refueling pattern, periodic large power peaking occurs, and when the special fuel assembly 2 is loaded with the same enrichment as the conventional example, the maximum Although the linear power density exceeds the limit value, conversely, by adopting the special fuel assembly 2 with a lower enrichment level, the power peaking of the special fuel assembly 2 can be obtained at the same level as the conventional one, and the irradiation test specimen The integrated amount of fast neutron irradiation can be secured.
本実施例の結果を第5図に示す。低濃度特殊燃料集合体
の採用により、出力ビーキング、すなわ(4)
ち、最大線出力密度は制限値内に入る。The results of this example are shown in FIG. By adopting the low concentration special fuel assembly, the power peaking, that is, (4), the maximum linear power density is within the limit value.
また、この時の領域出力は第6図に示す如く領域間で差
違はなくなる。Further, in this case, there is no difference in the area output between the areas as shown in FIG.
本発明により、】/4炉心回転対称燃料交換パターン採
用時の炉中心の出力ビーキングを他の燃料集合体を新た
に使用せずに低減出来、最大線出力密度を制限値内に抑
えることが出来る。また、特殊燃料集合体の濃縮度を低
減出来る。According to the present invention, it is possible to reduce the power peaking at the center of the reactor when adopting a /4 core rotationally symmetrical refueling pattern without newly using other fuel assemblies, and it is possible to suppress the maximum linear power density within the limit value. . Furthermore, the enrichment level of the special fuel assembly can be reduced.
第1図は従来例における燃料配置図、第2図は従来例に
おける燃料作ぎパターン図、第3図は本発明の実施例に
おける燃料配置図、第4図は同じく燃料交換パターン図
、第5図は本発明の実施例と、従来1/4燃料交換パタ
一ン採用時の出力ビーキング変化の線図、第6図は従来
例における領域出力変化の線図、第7図は本発明の実施
例における領域出力変化の線図である。
1・・・標準燃料集合体、2・・・特殊燃料集合体。
代理人 弁理士 高橋明夫
(5)
第1図Fig. 1 is a fuel arrangement diagram in the conventional example, Fig. 2 is a fuel production pattern diagram in the conventional example, Fig. 3 is a fuel arrangement diagram in the embodiment of the present invention, Fig. 4 is also a fuel exchange pattern diagram, and Fig. 5 The figure shows an example of the present invention and a diagram of the output peaking change when adopting the conventional 1/4 fuel exchange pattern, Figure 6 is a diagram of the area output change in the conventional example, and Figure 7 shows the example of the present invention. FIG. 3 is a diagram of area output changes in an example; 1...Standard fuel assembly, 2...Special fuel assembly. Agent Patent attorney Akio Takahashi (5) Figure 1
Claims (1)
する圧力管理型原子炉において、1/4炉心回転対称燃
料交換パターン採用時に、特殊燃料集合体は炉中心に装
荷することを特徴とする燃料の装荷方法。1. In a pressure-controlled nuclear reactor in which a special fuel assembly containing a member for monitoring pressure pipe material is loaded, the special fuel assembly is loaded in the center of the reactor when a 1/4 core rotationally symmetric fuel exchange pattern is adopted. How to load fuel.
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP59027105A JPS60171494A (en) | 1984-02-17 | 1984-02-17 | Method of charging fuel |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP59027105A JPS60171494A (en) | 1984-02-17 | 1984-02-17 | Method of charging fuel |
Publications (1)
Publication Number | Publication Date |
---|---|
JPS60171494A true JPS60171494A (en) | 1985-09-04 |
Family
ID=12211800
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
JP59027105A Pending JPS60171494A (en) | 1984-02-17 | 1984-02-17 | Method of charging fuel |
Country Status (1)
Country | Link |
---|---|
JP (1) | JPS60171494A (en) |
Cited By (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US6005905A (en) * | 1995-06-30 | 1999-12-21 | Hitachi, Ltd. | Initial core |
US9011195B2 (en) | 2011-12-23 | 2015-04-21 | Maximum Visibility Solutions, Llc | Collapsible balloon cup with attachable inflation air tube |
-
1984
- 1984-02-17 JP JP59027105A patent/JPS60171494A/en active Pending
Cited By (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US6005905A (en) * | 1995-06-30 | 1999-12-21 | Hitachi, Ltd. | Initial core |
US9011195B2 (en) | 2011-12-23 | 2015-04-21 | Maximum Visibility Solutions, Llc | Collapsible balloon cup with attachable inflation air tube |
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