JPH05188169A - Control rod for adjusting volume of moderator - Google Patents
Control rod for adjusting volume of moderatorInfo
- Publication number
- JPH05188169A JPH05188169A JP4074428A JP7442892A JPH05188169A JP H05188169 A JPH05188169 A JP H05188169A JP 4074428 A JP4074428 A JP 4074428A JP 7442892 A JP7442892 A JP 7442892A JP H05188169 A JPH05188169 A JP H05188169A
- Authority
- JP
- Japan
- Prior art keywords
- core
- control rod
- moderator
- zircaloy
- volume adjustment
- 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.)
- Withdrawn
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
Abstract
Description
【０００１】[0001]
【産業上の利用分野】本発明は、原子炉の運転中に炉心
内の中性エネルギスペクトルを変えて炉心の反応度を増
加し、炉心の寿命延長を図る、いわゆるスペクトル移動
型原子炉に用いられる減速材体積調整制御棒に関するも
のである。BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention is used in a so-called spectrum transfer type nuclear reactor in which the neutral energy spectrum in the core is changed during the operation of the reactor to increase the reactivity of the core to extend the life of the core. The present invention relates to a speed reducer volume adjustment control rod.
【０００２】[0002]
【従来の技術】従来、減速材体積調整制御棒は、その全
長にわたりジルカロイの丸棒から成るもの、又は、ジル
カロイ被覆材にジルカロイの環状ペレットが封入された
ものであって、その外径は炉心挿入部の全長にわたり同
一寸法であり、特に中性子吸収材は使用していなかっ
た。このため、この制御棒を炉心寿命の後半において全
引抜きにすると、水対ウランの比が大きくなるので、中
性子エネルギスペクトルが熱中性子側に移動して、炉心
反応度が増加すると共に、軸方向中性子束分布も炉心上
部に大きく歪むことになる。軸方向出力ピーキングＦZ
は、この制御棒引抜後に大きくなり、熱流束熱水路係数
ＦQ も大きくなり、制限値に余裕がなくなるという問題
が生ずる。2. Description of the Related Art Conventionally, moderator volume adjustment control rods are made of zircaloy round rods over the entire length thereof, or zircaloy coating pellets are filled with zircaloy annular pellets, the outer diameter of which is the core. The insert had the same dimensions over the entire length, and no neutron absorber was used. For this reason, if this control rod is fully withdrawn in the latter half of the core life, the ratio of water to uranium increases, and the neutron energy spectrum moves to the thermal neutron side, increasing the core reactivity and increasing the axial neutron. The bundle distribution will also be greatly distorted above the core. Axial output peaking F Z
Becomes larger after the control rod is pulled out, the heat flux heat water channel coefficient F Q also becomes larger, and there is a problem that the limit value has no margin.
【０００３】[0003]
【発明が解決しようとする課題】このように、大きな軸
方向出力ピーキングＦZ及び熱流束熱水路係数ＦQが生ず
ると、制限値に対して余裕がなくなるため、負荷追従運
転に制約が入る等、原子炉の運用に制限が課せられるの
で望ましくなく、ＦZ、ＦQの低減が求められていた。As described above, when a large axial output peaking F Z and a large heat flux heat flow channel coefficient F Q occur, there is no room for the limit value, so that the load following operation is restricted. etc., undesirable since restrictions on the operation of the reactor is imposed, F Z, reduction of F Q has been demanded.
【０００４】本発明は、上記の如き事情に鑑みてなされ
たものであって、従来の減速材体積調整制御棒の引抜後
に生ずる高い軸方向出力ピーキングＦZ を低減し平坦な
軸方向出力分布を炉心寿命の全般にわたって得ることを
目的としている。The present invention has been made in view of the above circumstances, and reduces the high axial output peaking F Z that occurs after the conventional moderator volume adjustment control rod is withdrawn, and reduces the flat axial output distribution. The purpose is to obtain the entire life of the core.
【０００５】[0005]
【課題を解決するための手段】上記目的を達成するため
に、本発明によるスペクトル移動用減速材体積調整制御
棒は、炉心有効部に全挿入される部分（炉心有効長部
分）の上側３０〜５０％に相当する上部部分を、ジルカ
ロイから構成し、炉心有効長部分の残部に相当する下部
部分を、ジルカロイの他にステンレス鋼又はハフニウム
材、銀−インジウム−カドミウム合金材等の中性子吸収
材を含むように構成して、下部部分の中性子吸収を上部
部分よりも強くすることを特徴としている。In order to achieve the above object, the moderator volume adjustment control rod for spectrum movement according to the present invention has an upper side 30 to 30 of a portion (core effective length portion) fully inserted into the core effective portion. The upper part corresponding to 50% is made of zircaloy, and the lower part corresponding to the rest of the effective core length is made of neutron absorbing material such as stainless steel or hafnium material, silver-indium-cadmium alloy material in addition to zircaloy. It is characterized in that the neutron absorption in the lower part is stronger than that in the upper part.
【０００６】また、本発明によると、上記目的は、中性
子エネルギスペクトルを変動すべく原子炉の炉心を構成
成する燃料集合体に対して挿入及び引抜きがされる減速
材体積調整制御棒において、炉心有効部に全挿入される
部分の上側３０〜５０％に相当する上部部分をジルカロ
イから構成すると共に、炉心有効部に全挿入される部分
の残部に相当する下部部分をジルカロイから構成し、前
記上部部分の水平断面積を、前記下部部分の水平断面積
の５０〜８０％とすることによっても達成される。Further, according to the present invention, the above object is to provide a moderator volume adjustment control rod which is inserted into and withdrawn from a fuel assembly constituting a reactor core so as to change a neutron energy spectrum. The upper part corresponding to 30 to 50% of the upper side of the part fully inserted into the effective part is made of zircaloy, and the lower part corresponding to the remaining part of the part fully inserted into the core effective part is made of zircaloy. It is also achieved by making the horizontal cross-sectional area of the part 50% to 80% of the horizontal cross-sectional area of the lower part.
【０００７】[0007]
【作用】減速材体積調整制御棒は、炉心寿命の前半は炉
心内に全挿入しておき、炉心寿命の後半は炉心から全引
抜きした状態で用いる。本発明による制御棒では、炉心
下側約５０〜７０％に相当する下部部分に中性子吸収材
が加えられているか、又は炉心上側約３０〜５０％に相
当する上部部分のみ水体積割合が多いために、挿入状態
では軸方向出力分布が炉心上部に歪むことになり、軸方
向の燃焼度としては炉心上部の方がより進むため、その
後の引抜状態では炉心上部での出力が抑制され軸方向出
力分布の大きな変動が避けられることになる。The moderator volume adjustment control rod is used in a state in which it is fully inserted into the core during the first half of the core life, and is completely pulled out from the core during the latter half of the core life. In the control rod according to the present invention, the neutron absorbing material is added to the lower part corresponding to the core lower side of about 50 to 70%, or only the upper part corresponding to the core upper side of about 30 to 50% has a large water volume ratio. In addition, in the inserted state, the axial power distribution is distorted in the upper part of the core, and the axial burnup is higher in the upper part of the core, so in the subsequent drawing state, the output in the upper part of the core is suppressed and the axial output is reduced. Large fluctuations in the distribution will be avoided.
【０００８】次に、本発明の好適な実施例について添付
図面を参照して詳細に説明するが、図中、同一符号は同
一又は対応部分を示すものとする。Next, preferred embodiments of the present invention will be described in detail with reference to the accompanying drawings. In the drawings, the same reference numerals indicate the same or corresponding parts.
【０００９】[0009]
【実施例】図１は、本発明の一実施例によるスペクトル
移動用減速材体積調整制御棒が挿入された燃料集合体の
横断面図であり、図２は、図１のＡ−Ａ線に沿っての断
面図である。図中、符号１は燃料集合体、符号２は燃料
集合体１を構成する燃料棒、符号３は本発明による減速
材体積調整制御棒、符号４は制御棒３を案内するための
案内管である。本発明による減速材体積調整制御棒３
は、図示しないが、スパイダによって束ねられて制御棒
集合体を構成する。1 is a cross-sectional view of a fuel assembly in which a moderator volume adjustment control rod for spectrum movement according to an embodiment of the present invention is inserted, and FIG. 2 is a line AA of FIG. It is sectional drawing along. In the figure, reference numeral 1 is a fuel assembly, reference numeral 2 is a fuel rod that constitutes the fuel assembly 1, reference numeral 3 is a moderator volume adjusting control rod according to the present invention, and reference numeral 4 is a guide tube for guiding the control rod 3. is there. Moderator volume adjustment control rod 3 according to the present invention
Although not shown, are bundled by a spider to form a control rod assembly.
【００１０】図２に明示するように、本発明による減速
材体積調整制御棒３は、炉心有効長部分の上側約３０〜
５０％に相当する部分（以下、「上部部分」という）３
ａの中性子吸収性よりも炉心下側約５０〜７０％に相当
する部分(以下、「下部部分」という）３ｂの中性子吸収
性が強化されるよう、上部部分３ａと下部部分３ｂとで
構成が異なっている。その構成としては種々あるが、例
えば図３及び図４に示すように、上部部分３ａをジルカ
ロイの中実棒５とし、下部部分３ｂをジルカロイ丸棒６
の周囲に中性子吸収材であるステンレス鋼の被覆材７を
付けたものが考えられる。或は、上部部分３ａを、図５
に示すように、ジルカロイ被覆管８内に中空ジルカロイ
ペレット９を封入した構成とし、下部部分３ｂを、図６
に示すように、ジルカロイ又はステンレス鋼から成る被
覆管１０内に中空ジルカロイペレット１１を封入し、更
にその中に、ステンレス鋼、銀−インジウム−カドミウ
ム合金、ハフニウム、エルビウム又はボロン・カーバイ
ド等の中性子吸収材１２を封入した構成としても良い。
更に、図示しないが、図６に示す下部部分３ｂでは、ジ
ルカロイペレット間に薄いステンレス鋼円板を挿入して
も良い。As clearly shown in FIG. 2, the moderator volume adjusting control rod 3 according to the present invention has an upper portion of the effective core length of about 30 to 30.
A portion corresponding to 50% (hereinafter referred to as "upper portion") 3
The upper portion 3a and the lower portion 3b are configured so that the neutron absorptivity of a portion (hereinafter, referred to as "lower portion") 3b corresponding to about 50 to 70% below the neutron absorptivity of a is enhanced. Different. There are various configurations, but for example, as shown in FIGS. 3 and 4, the upper portion 3a is a solid rod 5 of zircaloy and the lower portion 3b is a zircaloy round rod 6.
It is conceivable that a coating material 7 of stainless steel, which is a neutron absorber, is attached to the periphery of the. Alternatively, the upper portion 3a is shown in FIG.
As shown in FIG. 6, a hollow zircaloy pellet 9 is enclosed in a zircaloy cladding tube 8, and the lower portion 3b is shown in FIG.
, A hollow zircaloy pellet 11 is enclosed in a cladding tube 10 made of zircaloy or stainless steel, and neutron absorption such as stainless steel, silver-indium-cadmium alloy, hafnium, erbium or boron carbide is contained therein. The material 12 may be enclosed.
Further, although not shown, in the lower portion 3b shown in FIG. 6, thin stainless steel discs may be inserted between the zircaloy pellets.
【００１１】別の実施例では、図９に示すように、前記
上部部分３ａの外径のみ断面積の約２０〜５０％に相当
するだけ減少することにより、上部部分における水体積
割合を増加して炉心上部部分と下部部分での水対ウラン
比を調整して軸方向出力分布を上部へ歪ませている。図
１０は図９の横断面図を例示している。In another embodiment, as shown in FIG. 9, only the outer diameter of the upper portion 3a is reduced by about 20 to 50% of the cross-sectional area to increase the water volume ratio in the upper portion. The axial power distribution is distorted upward by adjusting the water-to-uranium ratio in the upper and lower parts of the core. FIG. 10 illustrates the cross-sectional view of FIG.
【００１２】このような減速材体積調整制御棒３の上部
部分３ａと下部部分３ｂとの構成の違いにより、減速材
体積調整制御棒３を炉心、即ち燃料集合体１の案内管４
内に全挿入すると、軸方向中性子束を上側に歪ませる効
果がある。この効果は、中性子吸収材を利用した実施例
でも、外径を減少する実施例でもほぼ同等に得られるこ
とが確認されている。Due to the difference in structure between the upper portion 3a and the lower portion 3b of the moderator volume adjustment control rod 3 as described above, the moderator volume adjustment control rod 3 is provided in the core, that is, the guide tube 4 of the fuel assembly 1.
When fully inserted, it has the effect of distorting the axial neutron flux upward. It has been confirmed that this effect can be obtained almost equally in the example using the neutron absorber and the example in which the outer diameter is reduced.
【００１３】図７は、炉心上半分の相対出力と炉心下半
分の相対出力の差の指標であるアキシャル・オフセット
と、サイクル燃焼度との関係を示すグラフである。この
図から理解されるように、従来の減速材体積調整制御棒
の場合、炉心寿命の前半（図７において符号２０で示す
部分）に全挿入した状態では、軸方向出力分布は下側に
歪み、燃焼度分布は炉心下部がより燃焼した分布とな
る。このため、炉心寿命の後半（図７において符号２１
で示す部分）でこの従来の制御棒を全引抜きにすると、
軸方向出力分布が炉心上部に大きく歪むという問題があ
った。しかし、本発明による減速材体積調整制御棒３で
は、全挿入状態では若干炉心上側に歪むだけであるの
で、全引抜きにした状態では、逆に炉心上側に歪むこと
は少なくなるという利点がある。FIG. 7 is a graph showing the relationship between the cycle burnup and the axial offset which is an index of the difference between the relative power in the upper half of the core and the relative power in the lower half of the core. As can be seen from this figure, in the case of the conventional moderator volume adjustment control rod, the axial power distribution is distorted downward when fully inserted in the first half of the core life (the portion indicated by reference numeral 20 in FIG. 7). The burnup distribution is such that the lower part of the core burns more. Therefore, the latter half of the core life (reference numeral 21 in FIG. 7)
If you pull out all the conventional control rods,
There was a problem that the axial power distribution was greatly distorted above the core. However, in the moderator volume adjustment control rod 3 according to the present invention, since it is only slightly distorted to the upper side of the core in the fully inserted state, there is an advantage that the distorted state to the upper side of the core is reduced in the fully drawn state.
【００１４】また、図８は、平均出力を１とした場合の
軸方向出力ピーキングＦZ と、サイクル燃焼度との関係
を示すグラフであるが、この図から明らかなように、従
来の制御棒を用いた場合には炉心上部側に大きく歪んだ
軸方向出力分布が、本発明の制御棒を使用すると、平坦
な軸方向出力分布となる。従って、軸方向出力ピーキン
グＦZ も大幅に低下することができ、結果として三次元
的出力ピーキングである熱流束熱水路係数ＦQも大幅に
低減できる。FIG. 8 is a graph showing the relationship between the axial output peaking F Z and the cycle burnup when the average output is set to 1. As is apparent from this graph, the conventional control rod is shown. When the control rod of the present invention is used, the axial power distribution greatly distorted to the upper side of the core becomes flat when the control rod of the present invention is used. Therefore, the axial output peaking F Z can be significantly reduced, and as a result, the heat flux thermal water channel coefficient F Q, which is three-dimensional output peaking, can also be significantly reduced.
【００１５】図７及び図８の例では、特に減速材体積調
整制御棒３の下部部分３ｂの中性子吸収効果を、上部部
分３ａに比較して反応度にして約０.６〜１.０％Δρ程
度付加することが最も有効と判断できるが、これは前述
のステンレス鋼材をジルカロイ材に混在して構成するこ
とにより達成することができる。また、各種の反応度効
果を変化させることも材料及び寸法の選択で可能であ
る。In the examples of FIGS. 7 and 8, the neutron absorption effect of the lower portion 3b of the moderator volume adjustment control rod 3 is about 0.6 to 1.0% in reactivity as compared with the upper portion 3a. It can be judged that the addition of about Δρ is most effective, but this can be achieved by mixing the above-mentioned stainless steel material with the zircaloy material. It is also possible to change various reactivity effects by selecting materials and dimensions.
【００１６】上部部分の外径を減少する場合には、断面
積の約２０〜５０％減少するのが最も有効である。When reducing the outer diameter of the upper portion, it is most effective to reduce the cross-sectional area by about 20 to 50%.
【００１７】[0017]
【効果】以上のように、本発明の減速材体積調整制御棒
によれば、全挿入期間及び全引抜期間を通じて軸方向出
力分布の平坦化が達成され、軸方向出力ピーキング ＦZ
及び熱流束熱水路係数ＦQの低減が可能となる。従っ
て、安全解析からのＦQ制限値に大幅な余裕が生ずるの
で、各種の負荷追従運転等が自由にできるようになると
共に、将来的に定格出力の増加等の可能性も出てくるな
ど、運転性向上及び性能向上が期待できる。[Effect] As described above, according to the moderator volume adjustment control rod of the present invention, the axial output distribution is flattened during the entire insertion period and the entire extraction period, and the axial output peaking F Z
Also, it is possible to reduce the heat flux / heat channel coefficient F Q. Accordingly, the resulting a significant margin in F Q limit value from the safety analysis, together with various load following operation or the like will be able to freely and future come out the possibility of an increase of the rated output, It can be expected to improve drivability and performance.
【００１８】また、製造面及び経済性でも特に大きな問
題となる点もないので、容易に従来技術に置き換えるこ
とができる。Since there is no particular problem in terms of manufacturing and economy, the conventional technique can be easily replaced.
【図１】本発明による減速材体積調整制御棒が挿入され
た燃料集合体を概略的に示す横断面図である。FIG. 1 is a cross-sectional view schematically showing a fuel assembly having a moderator volume adjustment control rod inserted therein according to the present invention.
【図２】図１のＡ−Ａ線に沿っての断面図である。FIG. 2 is a cross-sectional view taken along the line AA of FIG.
【図３】本発明による減速材体積調整制御棒の上部部分
の構成例を示す、図２のＢ−Ｂ線に沿っての断面図であ
る。3 is a cross-sectional view taken along line BB of FIG. 2, showing a structural example of an upper portion of a moderator volume adjustment control rod according to the present invention.
【図４】本発明による減速材体積調整制御棒の下部部分
の構成例を示す、図２のＣ−Ｃ線に沿っての断面図であ
る。FIG. 4 is a cross-sectional view taken along line C-C in FIG. 2, showing a structural example of a lower portion of the moderator volume adjustment control rod according to the present invention.
【図５】本発明による減速材体積調整制御棒の上部部分
の別の構成例を示す、図２のＢ−Ｂ線に沿っての断面図
である。5 is a cross-sectional view taken along the line BB of FIG. 2, showing another example of the configuration of the upper portion of the moderator volume adjustment control rod according to the present invention.
【図６】本発明による減速材体積調整制御棒の下部部分
の別の構成例を示す、図２のＣ−Ｃ線に沿っての断面図
である。FIG. 6 is a cross-sectional view taken along the line C-C of FIG. 2, showing another configuration example of the lower portion of the moderator volume adjustment control rod according to the present invention.
【図７】本発明による減速材体積調整制御棒の効果を示
す、アキシャル・オフセットとサイクル燃焼度の関係の
グラフである。FIG. 7 is a graph showing the relationship between axial offset and cycle burnup showing the effect of the moderator volume adjustment control rod according to the present invention.
【図８】本発明による減速材体積調整制御棒の効果を示
す、軸方向出力ピーキング ＦZとサイクル燃焼度の関係
のグラフである。FIG. 8 is a graph of the relationship between axial output peaking F Z and cycle burnup showing the effect of the moderator volume adjustment control rod according to the present invention.
【図９】本発明の他の実施例に係る減速材体積調整制御
棒の側面図である。FIG. 9 is a side view of a moderator volume adjustment control rod according to another embodiment of the present invention.
【図１０】図９におけるＤ−Ｄ及びＥ−Ｅ線に沿っての
水平断面図である。10 is a horizontal sectional view taken along the lines DD and EE in FIG.
【符号の説明】 １ 燃料集合体 ２ 燃料棒 ３ 減速材体積調整制御棒 ３ａ 上部部分 ３ｂ 下部部分 ４ 案内管 ５ ジルカロイ中実棒[Explanation of reference numerals] 1 fuel assembly 2 fuel rod 3 moderator volume adjustment control rod 3a upper part 3b lower part 4 guide tube 5 zircaloy solid rod
Claims (2)
原子炉の炉心を構成する燃料集合体に対して挿入及び引
抜きがされる減速材体積調整制御棒において、炉心有効
部に全挿入される部分の上側３０〜５０％に相当する上
部部分をジルカロイから構成すると共に、炉心有効部に
全挿入される部分の残部に相当する下部部分を中性子吸
収材を含むように構成し、前記下部部分の中性子吸収を
前記上部部分よりも強くしたことを特徴とする減速材体
積調整制御棒。1. A moderator volume adjustment control rod that is inserted into and extracted from a fuel assembly that constitutes a core of a nuclear reactor so as to change a neutron energy spectrum. The upper part corresponding to 30 to 50% is made of Zircaloy, and the lower part corresponding to the rest of the part fully inserted in the core effective part is configured to include a neutron absorber, and the neutron absorption of the lower part is A moderator volume adjustment control rod, which is stronger than the upper portion.
原子炉の炉心を構成成する燃料集合体に対して挿入及び
引抜きがされる減速材体積調整制御棒において、炉心有
効部に全挿入される部分の上側３０〜５０％に相当する
上部部分をジルカロイから構成すると共に、炉心有効部
に全挿入される部分の残部に相当する下部部分をジルカ
ロイから構成し、前記上部部分の水平断面積を、前記下
部部分の水平断面積の５０〜８０％としたことを特徴と
する減速材体積調整制御棒。2. A moderator volume adjustment control rod, which is inserted into and withdrawn from a fuel assembly forming a core of a nuclear reactor so as to change a neutron energy spectrum, of a portion entirely inserted into an effective core of the core. The upper part corresponding to the upper side 30 to 50% is composed of zircaloy, and the lower part corresponding to the rest of the part fully inserted into the core effective part is composed of zircaloy, and the horizontal cross-sectional area of the upper part is defined as the lower part. A moderator rod for adjusting volume of a moderator, characterized in that the horizontal sectional area of the portion is 50 to 80%.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP4074428A JPH05188169A (en) | 1991-11-15 | 1992-03-30 | Control rod for adjusting volume of moderator |
Applications Claiming Priority (3)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP3-300506 | 1991-11-15 | ||
| JP30050691 | 1991-11-15 | ||
| JP4074428A JPH05188169A (en) | 1991-11-15 | 1992-03-30 | Control rod for adjusting volume of moderator |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPH05188169A true JPH05188169A (en) | 1993-07-30 |
Family
ID=26415573
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP4074428A Withdrawn JPH05188169A (en) | 1991-11-15 | 1992-03-30 | Control rod for adjusting volume of moderator |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH05188169A (en) |
Cited By (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2002534693A (en) * | 1998-12-30 | 2002-10-15 | フラマトム | Reactor absorption rod |
| JP2013521492A (en) * | 2010-03-01 | 2013-06-10 | ウェスティングハウス エレクトリック スウェーデン アーベー | Neutron absorber and method for the production of neutron absorber |
| CN103778972A (en) * | 2014-02-24 | 2014-05-07 | 中国科学院合肥物质科学研究院 | Control rod assembly comprising axial partition control rod and heavy metal absorber rod |
| CN105957561A (en) * | 2016-07-05 | 2016-09-21 | 上海核工程研究设计院 | Control rod mechanism |
-
1992
- 1992-03-30 JP JP4074428A patent/JPH05188169A/en not_active Withdrawn
Cited By (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2002534693A (en) * | 1998-12-30 | 2002-10-15 | フラマトム | Reactor absorption rod |
| JP2013521492A (en) * | 2010-03-01 | 2013-06-10 | ウェスティングハウス エレクトリック スウェーデン アーベー | Neutron absorber and method for the production of neutron absorber |
| CN103778972A (en) * | 2014-02-24 | 2014-05-07 | 中国科学院合肥物质科学研究院 | Control rod assembly comprising axial partition control rod and heavy metal absorber rod |
| CN105957561A (en) * | 2016-07-05 | 2016-09-21 | 上海核工程研究设计院 | Control rod mechanism |
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Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| A300 | Withdrawal of application because of no request for examination |
Free format text: JAPANESE INTERMEDIATE CODE: A300 Effective date: 19990608 |