JPS63250588A - Fuel aggregate containing partial long-sized gadolinium - Google Patents
Fuel aggregate containing partial long-sized gadoliniumInfo
- Publication number
- JPS63250588A JPS63250588A JP62084687A JP8468787A JPS63250588A JP S63250588 A JPS63250588 A JP S63250588A JP 62084687 A JP62084687 A JP 62084687A JP 8468787 A JP8468787 A JP 8468787A JP S63250588 A JPS63250588 A JP S63250588A
- Authority
- JP
- Japan
- Prior art keywords
- gadolinium
- fuel
- length
- core
- axial
- 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.)
- Granted
Links
- 239000000446 fuel Substances 0.000 title claims description 66
- 229910052688 Gadolinium Inorganic materials 0.000 title claims description 40
- UIWYJDYFSGRHKR-UHFFFAOYSA-N gadolinium atom Chemical compound [Gd] UIWYJDYFSGRHKR-UHFFFAOYSA-N 0.000 title claims description 40
- 239000008188 pellet Substances 0.000 claims description 17
- 238000002485 combustion reaction Methods 0.000 description 6
- 230000000712 assembly Effects 0.000 description 5
- 238000000429 assembly Methods 0.000 description 5
- 230000009257 reactivity Effects 0.000 description 4
- 238000010586 diagram Methods 0.000 description 3
- 238000000034 method Methods 0.000 description 3
- ZOXJGFHDIHLPTG-UHFFFAOYSA-N Boron Chemical compound [B] ZOXJGFHDIHLPTG-UHFFFAOYSA-N 0.000 description 2
- 238000010521 absorption reaction Methods 0.000 description 2
- 229910052796 boron Inorganic materials 0.000 description 2
- 238000004364 calculation method Methods 0.000 description 2
- 239000002826 coolant Substances 0.000 description 2
- 239000002574 poison Substances 0.000 description 2
- 231100000614 poison Toxicity 0.000 description 2
- 229910052770 Uranium Inorganic materials 0.000 description 1
- 238000009792 diffusion process Methods 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 238000005516 engineering process Methods 0.000 description 1
- 239000006260 foam Substances 0.000 description 1
- CMIHHWBVHJVIGI-UHFFFAOYSA-N gadolinium(III) oxide Inorganic materials [O-2].[O-2].[O-2].[Gd+3].[Gd+3] CMIHHWBVHJVIGI-UHFFFAOYSA-N 0.000 description 1
- 238000004519 manufacturing process Methods 0.000 description 1
- 239000000463 material Substances 0.000 description 1
- JFALSRSLKYAFGM-UHFFFAOYSA-N uranium(0) Chemical compound [U] JFALSRSLKYAFGM-UHFFFAOYSA-N 0.000 description 1
- 239000002699 waste material Substances 0.000 description 1
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-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
- Solid Fuels And Fuel-Associated Substances (AREA)
- Monitoring And Testing Of Nuclear Reactors (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】
〔産業上の利用分野〕
本発明は加圧水型原子炉（以下ＰＷＲと称す）の部分長
ガドリニウム入り燃料集合体に関するものである。DETAILED DESCRIPTION OF THE INVENTION [Field of Industrial Application] The present invention relates to a fuel assembly containing part-length gadolinium for a pressurized water nuclear reactor (hereinafter referred to as PWR).
原子炉の反応度制御は、制御棒クラスタ操作及び１次冷
却材中のほう素濃度調整の独立した２つの方法にて実施
している。これらの制御方式に加えて、炉心寿命初期に
おける余剰反応度制御及び高温出力運転状態で減速材温
度係数を負にするため、熱中性子の吸収断面積の大きい
物質（はう素）を含むパーナブルポイズン棒を使用して
いる。Reactor reactivity control is carried out using two independent methods: control rod cluster operation and boron concentration adjustment in the primary coolant. In addition to these control methods, in order to control excess reactivity at the early stage of core life and to make the moderator temperature coefficient negative in high-temperature output operating conditions, a parenable containing a material with a large thermal neutron absorption cross section (boron) is used. It uses a poison stick.
まｔこ、上記と同様の目的でバーナプルポイズン棒の廃
棄−物処理、燃料経済性等の観点よすＵ Ｏ，燃料ペレ
ットに熱中性子吸収断面積の大きいＧｄ２Ｏ３を混在し
たＵｏＬ燃料ペレットを充填した燃料棒（以下ガドリニ
ウム入り燃料棒と称す）による燃料集合体（以下ガドリ
ニウム入り燃料集合体と称す）の使用も行われようとし
ている。但し、とのガドリニウム入り燃料集合体は、取
替炉心（２サイクル目以降の炉心）での使用目的とし、
ガドリニウムが燃料有効長にわたって軸方向に均一分布
した燃料棒（以下、全長ガドリニウム入り燃料棒と称す
）を含む燃料集合体（以下、全長ガドリニウム入り燃料
集合体と称す）である。Matoko, for the same purpose as above, from the viewpoint of waste disposal of burner poison rods, fuel economy, etc.UO, filling fuel pellets with UoL fuel pellets mixed with Gd2O3, which has a large thermal neutron absorption cross section. Fuel assemblies (hereinafter referred to as gadolinium-containing fuel assemblies) using fuel rods (hereinafter referred to as gadolinium-containing fuel rods) are also being used. However, the gadolinium-containing fuel assembly is intended for use in a replacement core (core from the second cycle onwards).
This fuel assembly (hereinafter referred to as a full-length gadolinium-containing fuel assembly) includes fuel rods (hereinafter referred to as full-length gadolinium-containing fuel rods) in which gadolinium is uniformly distributed in the axial direction over the effective fuel length.
全長がトリニウム入り燃料集合体は、取替炉心に使用す
る場合については、装荷体数が少ないことなどにより、
燃焼に伴う軸方向出力分布の変化が比較的少ない。即ち
、第４図に取替炉心に全長ガドリニウム入り燃料集合体
を使用した場合の軸方向燃料計算の典型例のグラフを示
すが、アキシャルオフセット〔（炉心上半分の出力−炉
心下半分の出力）／（炉心上半分の出力子炉心下半分の
出力）を意味し、軸方向出力分布の歪み度の目安である
〕の振れ巾も小さ／、 、Ｆｚ （軸方向ピーキングフ
ァクターで、軸方向における相対平均出力の最大値）も
大きくなっておらず、核的に問題はない。When using fuel assemblies with trinium in the total length, when used in replacement cores, due to the small number of loaded bodies, etc.
There is relatively little change in the axial power distribution due to combustion. That is, Fig. 4 shows a graph of a typical example of axial fuel calculation when a full-length gadolinium-containing fuel assembly is used in the replacement core. / (means the output of the upper half of the core and the output of the lower half of the core), which is a measure of the skewness of the axial power distribution] is also small. The maximum value of average output has not increased, and there is no nuclear problem.
しかしながら、初装荷炉心の場合には、減速材温度係数
を負に保つ観点より全長ガドリニウム入り燃料集合体数
の使用量が多いこと及び炉心上・下端の冷却材温度差に
伴い、炉心上端でより大きな負の反応度帰還がかかり、
アキシャルオフセットが寿命初期において、かなり負側
（約−１０％）より燃焼が進むことにより、下部側のガ
ドリニウム（Ｇｄ）が上部側より早く燃え、軸方向出力
分布が大きく変化する。第５図にアキシャルオフセ ′
ット（Ａ、Ｏ，）及びＦｚの燃焼に伴う変化例を示す。However, in the case of an initially loaded core, from the viewpoint of keeping the moderator temperature coefficient negative, the number of full-length gadolinium-containing fuel assemblies used is large, and due to the difference in coolant temperature between the upper and lower ends of the core, A large negative reactivity feedback is applied,
At the beginning of the axial offset's life, combustion progresses from the negative side (approximately -10%), so that gadolinium (Gd) on the lower side burns faster than on the upper side, and the axial power distribution changes significantly. Figure 5 shows the axial offset ′
Examples of changes accompanying combustion of cut (A, O,) and Fz are shown.
アキシャルオフセットの振れ巾も大きく、Ｆｚも大きく
なり、炉心最高線出力密度の制御条件を逸脱する可能性
が生じている。The swing range of the axial offset is also large, and Fz is also large, creating the possibility that the control conditions for the core maximum linear power density will be deviated from.
また、ＰＷｒｔの軸方向出力分布制御法としては、通常
毎月アキシャルオフセットの目標値を定め、アキンヤル
オフセットが目標値±５％範囲内となるよう出力分布制
御を実施しているが、アキンヤルオフセットが急激に大
きく振れｔこ場合には、目標値を頻繁に変更する必要が
生（二、炉心管理上好ましくない。In addition, as a PWrt axial output distribution control method, a target value of axial offset is usually determined every month, and output distribution control is performed so that the axial offset is within the range of ±5% of the target value. In this case, it is necessary to change the target value frequently (2. This is not desirable in terms of core management.
本発明は上述した事情に鑑みてなされたもので、初装荷
炉心の時から使用するのに適当な部分長ガドリニウム入
り燃料集合体を提供せんとするものである。The present invention has been made in view of the above-mentioned circumstances, and it is an object of the present invention to provide a fuel assembly containing partial length gadolinium that is suitable for use from the time of initial loading of the reactor core.
本発明の部分長ガドリニウム入り燃料集合体数第１図に
示すように上・下部のｌｂ、ＩＣにガドリニウムなし燃
料ペレット（ｆｓ縮ウランによろＵＯ□ペレット）、中
央部１ａにはガドリニウム入り燃料ペレットを充填した
燃料棒（以下部分長ガドリニウム入り燃料棒と称す）よ
り構成されている。Number of fuel assemblies containing partial length gadolinium according to the present invention As shown in Fig. 1, fuel pellets without gadolinium (UO□ pellets based on fs uranium foam) are used in the upper and lower lb and IC, and fuel pellets containing gadolinium are used in the central part 1a. It consists of fuel rods filled with gadolinium (hereinafter referred to as partial-length gadolinium-filled fuel rods).
Ｘは燃料棒上部１ｂのガドリニウムなし燃料ペレットを
充填した長さ、Ｙは燃料棒下部ＩＣのガドリニウムなし
燃料ペレットを充填した長さ、Ｉは燃料棒の燃料を充填
した長さである燃料有効長で、燃料棒中央部１ａにはガ
ドリニウム入り燃料ペレットが充填されている。ガドリ
ニウムなし燃料ペレット部分はガドリニウム入り燃料ベ
レット部分に比べて反応度が高いのでＸの長さがＹの長
さより長くなるにつれてアキシャルオフセットは負側よ
り正側へ移行する。X is the length of the upper part 1b of the fuel rod filled with fuel pellets without gadolinium, Y is the length of the lower IC of the fuel rod filled with fuel pellets without gadolinium, and I is the length of the fuel rod filled with fuel, which is the effective fuel length. The central portion 1a of the fuel rod is filled with fuel pellets containing gadolinium. Since the gadolinium-free fuel pellet portion has a higher reactivity than the gadolinium-containing fuel pellet portion, as the length of X becomes longer than the length of Y, the axial offset shifts from the negative side to the positive side.
前記Ｘ、Ｙの割合は、炉心寿命初期の高温全出力及び平
衡キセノンの炉心状態でアキシャルオフセット（Ａ、０
．）が０％近傍、即ち、＋３％〉Ａ、Ｏ，＞−３％であ
るように設定すち。The ratio of X and Y is determined by the axial offset (A, 0
．． ) is set near 0%, that is, +3%>A, O,>-3%.
従って、本発明の部分長ガドリニウム入り燃料集合体の
構成は燃料の軸方向上・下部に、それぞれ所定長さにＵ
Ｏ，燃料ペレットを充填し、中央部にＧｄ２Ｏ，を混在
させたＵ０２燃料ペレットであるガドリニウム入り燃料
ペレットを充填したものである。Therefore, the structure of the partial length gadolinium-containing fuel assembly of the present invention is such that U is provided at a predetermined length at the top and bottom of the fuel in the axial direction.
The fuel pellets are filled with gadolinium-containing fuel pellets, which are U02 fuel pellets in which Gd2O is mixed in the center.
燃料棒の軸方向上・下部にガドリニウムを含まないＵ
０２燃料ペレットを充填するので、この上・下部の長さ
を炉心寿命初期のアキシャルオフセットが０％近傍とな
るように設定すると、炉心上半分の出力と、炉心下半分
の出力がほぼ均等となるので、炉心の上・下半分のガド
リニウムはほぼ均等に燃え、燃焼に伴う上・下半分のガ
ドリニウム残存度の差は比較的少なくなる。このことに
より、即燃焼に伴う軸方向出力分布の変化は少なくなる
。U that does not contain gadolinium in the upper and lower parts of the fuel rod in the axial direction
Since it is filled with 02 fuel pellets, if the lengths of the upper and lower parts are set so that the axial offset at the beginning of the core life is close to 0%, the output of the upper half of the core and the output of the lower half of the core will be approximately equal. Therefore, the gadolinium in the upper and lower halves of the core burns almost evenly, and the difference in residual gadolinium between the upper and lower halves due to combustion is relatively small. This reduces changes in the axial power distribution due to immediate combustion.
即ち、アキシャルオフセットの振れ巾は小さくなり、Ｆ
ｚも小さくなり、炉心最高線出力密度も小さくなる。−
〔実施例〕
以下、添付図に基づいて本発明の実施例を詳細に説明す
る。In other words, the swing width of the axial offset becomes smaller, and F
z also becomes smaller, and the maximum linear power density of the core also becomes smaller. - [Example] Hereinafter, an example of the present invention will be described in detail based on the accompanying drawings.
サイクル長さ１６ケ月の初装荷炉心について、−次元拡
散計算コードを使用して、第１図に示す燃料上部のガド
リニウムなしの燃料長ｘ１燃料捧下部のガドリニウムな
しの燃料長Ｙをパラメータにして検討した結果、前記初
装荷炉心に適した部分長ガドリニウム入り燃料棒の寸法
を第２図に示す。乙の場合、Ｘ＝２７．０ｃｍ５Ｙ＝１
６．２ｃｍ、（１＝３５４．８ｃｍ）となる。この場合
のアキシャルオフセット及びＦｚの燃焼度に伴う変化を
第３図に示す。図において破線は全長ガドリニウム入り
燃料棒の場合、実線はこの実施例の部分長ガドリニウム
入り燃料棒の場合で、ガドリニウム入りｌベレットに含
まれるガドリニウム（Ｇｄ ）のｗｔ％は６％で、従来
の全長ガドリ二つム入り燃料棒の場合のＧｄｗｔ％も同
様に６％である。第３図に示すように、部分長ガドリニ
ウム入り燃料棒を使用した場合、従来の全長ガドリニウ
ム入り燃料棒を使用した場合に比べ、Ｆｚ、 Ａ、０．
共に振れが少なくなっている。For an initially loaded core with a cycle length of 16 months, use a -dimensional diffusion calculation code and consider the fuel length without gadolinium in the upper part of the fuel x1 as shown in Figure 1, and the fuel length without gadolinium in the lower part of the fuel shaft Y as parameters. As a result, the dimensions of a partial length gadolinium-containing fuel rod suitable for the above-mentioned initial loading core are shown in FIG. In the case of B, X=27.0cm5Y=1
6.2cm, (1=354.8cm). FIG. 3 shows changes in the axial offset and Fz with burnup in this case. In the figure, the broken line is for the full-length gadolinium-containing fuel rod, and the solid line is for the partial-length gadolinium-containing fuel rod of this example. The Gdwt% in the case of the fuel rod with two gads is also 6%. As shown in FIG. 3, when a partial length gadolinium-containing fuel rod is used, Fz, A, 0.
In both cases, the fluctuation is reduced.
以上詳細に説明した本発明によれば、燃焼に伴う軸方向
出力分布の変化を抑制でき、炉心最高線出力密度制限の
逸脱の問題を解決することが可能である。また、アキシ
ャルオフセット（Ａ、Ｏ，）の振れ巾も小さくなり、炉
心管理が容易となる。According to the present invention described in detail above, it is possible to suppress changes in the axial power distribution due to combustion, and it is possible to solve the problem of deviation of the core maximum linear power density limit. Furthermore, the swing width of the axial offset (A, O,) is also reduced, making core management easier.
第１図は本発明の部分長ガドリニウム・燃料棒の説明図
、第２図は本発明の一実施例を示す部分長ガドリニウム
燃料棒の寸法図、第３図は同実施例と従来の全長ガドリ
ニウム入り燃料棒を初装荷炉心に使用した場合のＦｚ、
Ａ、Ｏ，対燃焼度のグラフ、第４図は従来の全長ガド
リニウム入り燃料棒を取替炉心に用いた場合の典型例を
示すＦｚ、 Ａ、Ｏ，対サイクル燃焼度のグラフ、第５
図は従来の全長ガドリニウム入り燃料棒を初装荷炉心に
使用した場合のＦｚ、 Ａ、Ｏ，対燃焼度のグラフであ
る。
１ａ 燃料棒中央部、１ｂ ・燃料棒上部、１ｃ・燃料
棒下部。Fig. 1 is an explanatory diagram of a partial length gadolinium fuel rod of the present invention, Fig. 2 is a dimensional diagram of a part length gadolinium fuel rod showing an embodiment of the present invention, and Fig. 3 is a diagram showing the same embodiment and a conventional full length gadolinium fuel rod. Fz when using fuel rods in the initial loading core,
Graph of burnup versus A, O, Figure 4 is a graph of burnup versus cycle of Fz, A, O, showing a typical example when conventional full-length gadolinium-containing fuel rods are used in the replacement core.
The figure is a graph of Fz, A, O, and burnup versus burnup when conventional full-length gadolinium-filled fuel rods are used in the initial loading core. 1a central part of fuel rod, 1b upper part of fuel rod, 1c lower part of fuel rod.
Claims (1)
２燃料ペレットを充填し、中央部にＧｄ＿２Ｏ＿３を混
在させたＵＯ＿２燃料ペレットであるガドリニウム入り
燃料ペレットを充填したことを特徴とする部分長ガドリ
ニウム入り燃料集合体。UO_ is placed at a predetermined length at the top and bottom of the fuel rod in the axial direction.
1. A partial-length gadolinium-containing fuel assembly characterized in that the gadolinium-containing fuel pellet is filled with gadolinium-containing fuel pellets, which are UO_2 fuel pellets in which Gd_2O_3 is mixed in the central part.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP62084687A JPH0640139B2 (en) | 1987-04-08 | 1987-04-08 | Fuel assembly with partial length gadolinia applied to pressurized water reactor |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP62084687A JPH0640139B2 (en) | 1987-04-08 | 1987-04-08 | Fuel assembly with partial length gadolinia applied to pressurized water reactor |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS63250588A true JPS63250588A (en) | 1988-10-18 |
| JPH0640139B2 JPH0640139B2 (en) | 1994-05-25 |
Family
ID=13837589
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP62084687A Expired - Lifetime JPH0640139B2 (en) | 1987-04-08 | 1987-04-08 | Fuel assembly with partial length gadolinia applied to pressurized water reactor |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH0640139B2 (en) |
Citations (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS60117182A (en) * | 1983-11-30 | 1985-06-24 | 株式会社東芝 | Fuel aggregate for boiling-water type reactor |
| JPS60205281A (en) * | 1984-03-30 | 1985-10-16 | 原子燃料工業株式会社 | Fuel aggregate for boiling-water type reactor |
-
1987
- 1987-04-08 JP JP62084687A patent/JPH0640139B2/en not_active Expired - Lifetime
Patent Citations (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS60117182A (en) * | 1983-11-30 | 1985-06-24 | 株式会社東芝 | Fuel aggregate for boiling-water type reactor |
| JPS60205281A (en) * | 1984-03-30 | 1985-10-16 | 原子燃料工業株式会社 | Fuel aggregate for boiling-water type reactor |
Also Published As
| Publication number | Publication date |
|---|---|
| JPH0640139B2 (en) | 1994-05-25 |
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