JPS5943384A - Control rod device for fast breeder - Google Patents

Control rod device for fast breeder

Info

Publication number
JPS5943384A
JPS5943384A JP57155040A JP15504082A JPS5943384A JP S5943384 A JPS5943384 A JP S5943384A JP 57155040 A JP57155040 A JP 57155040A JP 15504082 A JP15504082 A JP 15504082A JP S5943384 A JPS5943384 A JP S5943384A
Authority
JP
Japan
Prior art keywords
control rod
fuel
effective
length
control
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
Application number
JP57155040A
Other languages
Japanese (ja)
Other versions
JPH0350233B2 (en
Inventor
金戸 邦和
渡 孔男
周作 澤田
孝太郎 井上
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Hitachi Ltd
Original Assignee
Hitachi Ltd
Priority date (The priority date 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 date listed.)
Filing date
Publication date
Application filed by Hitachi Ltd filed Critical Hitachi Ltd
Priority to JP57155040A priority Critical patent/JPS5943384A/en
Publication of JPS5943384A publication Critical patent/JPS5943384A/en
Publication of JPH0350233B2 publication Critical patent/JPH0350233B2/ja
Granted legal-status Critical Current

Links

Classifications

    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

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】 本発明は、反応度制御の/ζめの中性子吸収材を内蔵し
た制御棒を用いる高速増殖炉用の制御棒装置に関するも
のである。
DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a control rod device for a fast breeder reactor using a control rod incorporating a /ζ neutron absorber for reactivity control.

液体金属ナトリウムを冷却材として用いる高速増殖炉に
おいては、原子炉の反応度制御手段として、通常中性子
吸収材を内蔵した制御棒を炉心に上方より挿入しまたり
引抜いたりする操作を実施する。第1図は、従来の典型
的な高速増殖炉における燃料集合体と挿入時及び引抜時
の制御棒との位置関係を表わす概念図である。第1図中
、右の図は燃料集合体を示し、中央の図は完全引抜状態
の制御棒、左の図は完全挿入状態の制御棒を示す。
In fast breeder reactors that use liquid metal sodium as a coolant, control rods containing neutron absorbers are usually inserted into and withdrawn from the reactor core from above to control the reactivity of the reactor. FIG. 1 is a conceptual diagram showing the positional relationship between a fuel assembly and a control rod during insertion and withdrawal in a typical conventional fast breeder reactor. In FIG. 1, the right figure shows the fuel assembly, the center figure shows the control rod in a fully withdrawn state, and the left figure shows the control rod in a fully inserted state.

1は燃料集合体、2は制御棒に内蔵された中性子吸収材
、3は燃料集合体1内の燃料棒、4は燃t−1棒3内に
装荷された核分裂性物質、5及び6は夫々燃料棒3内に
装荷さJまた上部及び下部軸方向ブランケット、7は核
分裂により生成する揮発性物質を収納する燃料棒内のガ
スプl/ナム、8は!1il1句11棒案内管である。
1 is a fuel assembly, 2 is a neutron absorber built into the control rod, 3 is a fuel rod in the fuel assembly 1, 4 is a fissile material loaded in the fuel t-1 rod 3, 5 and 6 are J and upper and lower axial blankets respectively loaded in the fuel rods 3, 7 is the gas p/num in the fuel rods that accommodates the volatile materials produced by nuclear fission, 8 is! 1il1 clause 11 rod guide tube.

第1図のように、従来では制御棒に内蔵さfq−でいる
有効中性子吸収材部2(以下、制御俸有効部と略する)
は、完全挿入状態においては態率−1イイ・2合体1中
の燃料棒3内の核分裂性物質装荷部4(以F、・燃料有
効部と略称する。)の全域をカバーする長さを有し、壕
だ完全引抜状態においては制御棒有効部2の下端が燃料
有効部4の上端に位置している。従って完全引抜状態で
制御棒有効部2の一部が、燃料有効部4の上部に記動さ
れた上部軸方向プランケット5の位置に存在するので、
通常運転中、中性子を無駄に吸収し、中性子経済が悪く
なる結果をもたらしている。記も、これを縫けるために
制御棒の有効部が燃料棒の七部輔b−向ブランケットの
上方にまで引上げられるように制fnll欅の駆41J
ストロークを1灸くとることが考えられるが、これは炉
心上部に設置される:ti制御欅制御機駆動機構化を招
くことになり、ひいては原子炉容器及び格納容器の大型
化につながり建設コストの大幅な増大をもたらす。
As shown in Fig. 1, conventionally, an effective neutron absorbing material section 2 (hereinafter abbreviated as control salary effective section) is built into a control rod.
is the length that covers the entire area of the fissile material loading part 4 (hereinafter referred to as F, ・Fuel effective part) in the fuel rod 3 in the fuel rod 3 in the fuel rod 3 in the fuel rod 1 in the fully inserted state. The lower end of the control rod effective section 2 is located at the upper end of the fuel effective section 4 when the trench is fully withdrawn. Therefore, in the fully withdrawn state, a part of the control rod effective section 2 is present at the position of the upper axial plunket 5 marked on the upper part of the fuel effective section 4.
During normal operation, neutrons are wasted and absorbed, resulting in poor neutron economy. Also, in order to sew this, the effective part of the control rod was pulled up above the seventh part of the fuel rod b-direction blanket.
It is conceivable to use one moxibustion stroke per stroke, but this would require the use of a ti control keyaki controller drive mechanism installed at the top of the reactor core, which would eventually lead to an increase in the size of the reactor vessel and containment vessel, reducing construction costs. resulting in a significant increase.

本発明の目的は、上述した従来の欠点をなくし、制御棒
駆1+J+ストロークの長尺化すなわち原を炉容器や格
納容器の大型化をもたらすことなく通常運転時の中性子
の無駄な吸収をなくl〜、中1′1子経済の向上ひいて
は原子炉の経済性向−トZを図ることのできる制御棒装
置をl、14供することにある。
The purpose of the present invention is to eliminate the above-mentioned conventional drawbacks, and to increase the length of the control rod drive 1 + J + stroke, i.e., to eliminate wasteful absorption of neutrons during normal operation without increasing the size of the reactor vessel or containment vessel. The object of the present invention is to provide a control rod device capable of improving the economy of a nuclear reactor and, ultimately, the economic efficiency of a nuclear reactor.

上記目的を達成するため、本発明の高速増殖炉用制御棒
装置は、制御棒に内蔵された中性子吸収材で与えられる
制御棒有効部の長さを燃料棒に内蔵された核分裂性物質
で与えられる燃料有効77Bの長さよりも短く17、月
つ制御棒の完全引抜状態において上記制御棒有効部の下
端を上パ(1燃A:1有効部の上端よりも上方に位置せ
しめるようにしたことを特徴とするものである。
In order to achieve the above object, the control rod device for a fast breeder reactor of the present invention provides a control rod effective section length that is given by the neutron absorbing material built into the control rod, by using the fissile material built into the fuel rod. The length of the effective fuel 77B is shorter than the length of the effective fuel 77B, and the lower end of the control rod effective part is positioned above the upper end of the upper part (1 fuel A: 1 effective part) when the control rod is completely withdrawn. It is characterized by:

第2図は、本発明に基づく制御n11棒有効部と燃料集
合体の長さ関係並びに制御棒の挿入及び引抜時のそれら
の位置関係を例示したものである。
FIG. 2 illustrates the length relationship between the control rod effective part and the fuel assembly and the positional relationship thereof when the control rod is inserted and withdrawn according to the present invention.

この図において、右、中央及び左の各図の表わすもの、
並びに各符号の示すものは第1図におりるのと同様であ
る。第2図に明らかなように制御棒有効部2の長さは・
燃料有効部4の閘さより短く作られており、制御棒有効
部2の下端は完全挿入状態において燃料有効部4の下端
1で悼し7ておらず、また完全引抜状態において燃料有
効部4の上端よりも1.にイ1装置している。
In this figure, what the right, center, and left figures represent,
Also, each symbol indicates the same as in FIG. As is clear from Fig. 2, the length of the control rod effective section 2 is
It is made shorter than the width of the fuel effective section 4, and the lower end of the control rod effective section 2 does not touch the lower end 1 of the fuel effective section 4 in the fully inserted state, and also does not touch the lower end 1 of the fuel effective section 4 in the fully withdrawn state. 1. than the upper end. I have one device in place.

このJ合、完全挿入状態に↓?いて制御棒有効部2の上
端が燃料有効部4の下端に到達していないことが、その
間の中性f東分布(あるいは出力分布)の局所的な歪み
を招くと心配されるかも知れないが、高床炉においては
中性r−の平均自由<−i程か同いので、熱中性子炉に
見られるような中性r東の−に記局所的な歪みは発生し
ない。また制御棒fT効部2の1(さを短くすることに
より生じる全tlil171111可能反応度の低トな
」、制+1lll棒fr ’kh部2内の中ゼlF吸収
物′l僅の濃度を高めることにより対処することができ
る。
This J match is completely inserted ↓? There may be concerns that the fact that the upper end of the control rod effective section 2 does not reach the lower end of the fuel effective section 4 may cause local distortion of the neutral f east distribution (or power distribution) during that time. , in the high-bed reactor, the mean freedom of the neutral r- is the same as <-i, so no local distortion occurs in the - of the neutral r- as seen in thermal neutron reactors. In addition, by shortening the length of the control rod fT effect section 2, the total reactivity is lowered, and the concentration of the medium F absorbent in the control rod fr'kh section 2 is increased. This can be dealt with by

次((−・ト発明に]、(づき「vl(の(i”−i 
Ii’i’、な・採ることにより、中+′1子経済1−
どの(′1冒Wの利点があるか4定1目的にノドすど′
41、に、制御’l(I棒イ1効部のt(ノ尺化の望ま
しい範囲を第:3図を8照L2で明らかにしよう。
Next ((-・to invention),
Ii'i', by taking the middle + '1 child economy 1-
Which one has the advantage of 1 adventure?
41, let us clarify the desirable range of control 'l (I rod A 1 effective part t) in Figure 3 with 8 light L2.

第3図Q」1、R11l flD’棒イ!効部2の挿入
に伴なう制σ11(仝の制御′111I川能反応用rl
の相対的・体化をグラノ化したものであり、11へ軸は
′フ、:全引回11p7を0と17だ挿入深さを相対値
で表わし、縦軸は制御可能反応度の相対値を表わしてい
る。図中、実線は従来例の場合、破線は本発明に基づ0
た場合を示−10実線のグラフより明らかな通り、従来
例においては、挿入深さ0%すなわち完全引抜状態に4
3・いても、制御棒の制御可能反応度は完全挿入時の反
応度に対して2%残っており、これは完全挿入時の中性
子吸収31.の2チが冗全引抜時でも無駄に吸収されて
いることを、?に味する。これを電気出力100 万k
W N (7) 413fJJ、 的す高速増<11+
炉ノI、’r ツ反応18゜の絶体値を基に換2すする
と、制御棒の全制御iiJ’能反応度は10〜12チΔ
に/に程度であり、無駄吸収分の制御可能反応度は0.
2〜0.24%Δに/にとなる。
Figure 3 Q'1, R11l flD'stick! Control σ11 due to insertion of effective part 2 (this control '111I river function reaction rl
The axis to 11 is 0 and 17. The insertion depth is expressed as a relative value, and the vertical axis is the relative value of controllable reactivity. It represents. In the figure, the solid line is for the conventional example, and the broken line is for the present invention.
As is clear from the -10 solid line graph, in the conventional example, the insertion depth is 0%, that is, the fully pulled out state is 4.
3. Even if the control rod is fully inserted, the controllable reactivity of the control rod remains 2% of the reactivity when fully inserted, and this is due to the neutron absorption when fully inserted. Is it true that the two channels are being absorbed in vain even during redundant extraction? taste. This is an electrical output of 1 million k.
W N (7) 413fJJ, target high speed increase <11+
Based on the absolute value of the reactor I,'r reaction 18°, the total control rod iiJ' reactivity is 10 to 12 chi Δ.
The controllable reactivity of waste absorption is about 0.
2 to 0.24% Δ.

一方、原子炉を一年間IM(転する為に必°決な反lム
度は、炉心構成によりかなりの差は存(1−するが、2
5〜6%Δに/に程度であり、これに対して無11i1
<吸収分は3〜10チを占めることになる。原子炉の設
イf:h利用率を80チと仮定して、この無駄吸収分を
1j11転日数に揮11すると9〜30日にも及ぶ。こ
れは、送電売価を約15 i’J/kW−hrと見た場
合、年間3()億〜10 Q fは円の売上減少を次味
する。
On the other hand, there are considerable differences in the degree of lumen needed to convert a nuclear reactor to IM for one year depending on the core configuration (1-1, 2-2).
It is about 5-6% Δ, whereas no 11i1
<Absorption will account for 3 to 10 inches. Assuming that the reactor installation f:h utilization rate is 80, and if this waste absorption is calculated as 1j11 transfer days, it will amount to 9 to 30 days. If we consider the electricity transmission sales price to be about 15 i'J/kW-hr, this means a decrease in sales of 300 million to 10 Qf per year.

と5ンzに対し5、破線のグラフから明らかなように、
+発明による一1局合には挿入深さ0係ずなわら完全引
抜状態1においで制御外の制御1耳能JX1.応度は無
+11得る(マ度に小さいものとなるので、上記従来例
の鳴合の如き無駄な中性子吸収、そilによる運転可能
日数の減少、送′醒売トの減少を僻けることができる。
and 5 for 5 z, as is clear from the broken line graph,
+ In the 11th position according to the invention, the control 1 ear function JX 1. which is outside the control in the completely withdrawn state 1 regardless of the insertion depth 0. (Since it is extremely small, it is possible to avoid wasteful neutron absorption such as the ringing in the conventional example described above, a decrease in the number of days of operation due to the noise, and a decrease in the number of unloaded units.) can.

房だ、これは逆に、同一運転日数で考えると、燃、FI
有効部4内の(へ分裂性物′ν↓の装4ニー!I籠を反
161JQ 、lf* ;’)、 f 3〜10チ減少
させ(8るという利点カ得られるととを扁味している。
On the contrary, if you consider the same number of driving days, fuel and FI
In the effective part 4 (the 4 knee!I basket of the fissionable substance ′ν↓ is anti-161JQ, lf* ;'), f is reduced by 3 to 10 chi (the advantage of 8 is obtained). are doing.

第:3図において、実線のグラフを挿入深さの負側へ々
)挿することにより、中性子1j4’、 t’ik吸収
減少効川を奏用するには制御棒有効部2を燃料有効部4
よりもどの稈り庄のt+さだけtノ尺化−111,ばよ
いかについでの1!’j ’Th’E限Vf−値が得ら
れる。このt(z尺化限界値は第3図によると−15%
挿入深さ程度に相当する硬さだシ)の短尺化であること
がわかる。このことか1゛]考え−こ、υ1jI(!I
的f!、高克・I増殖原子炉の1や11として、燃料イ
j′乃部4のf−jさl 00 an % 上¥XB 
1it−+方向ブランフット5の昆さ351なる炉心を
想定すると、制御棒有効部2の短尺化を約15mすなわ
ち−L部輔方向ブランケットの」φさの棒程度以上にし
、−r’もほとんど中性子無駄吸収減少効果の一層の向
上を・もたらすことにはならないことがわかる。即ち、
中性子無駄吸収減少効果を奏するには、制御棒有効部2
は燃料有効部4に比べて、上部軸lj向グランケット5
0暴さのlAよりも小さい長さだけ短かければ十分であ
ることがわかる1、 なお、核分裂により生成される揮発性物質を収納するが
スプレナノ、7を燃料有効部4よりも1一方に配置する
いわ(す〕る上部がスゾレナム方式の燃料棒を用いた炉
心では、燃料有効部4の全体が第1及び2図の場合より
も下方に配置されるので、制御棒の駆動ストロークに対
する制限が若干なく−+11される傾向があると一般に
試われでいるが、本発明によれば、このような駆動スト
ロークの制限へ?工ξ′+11に期待せずとも完全引抜
状態において制f+QI棒有効部2の下端を燃Vat有
効部4の一ト端イ)7置よりもトノjに置くことができ
、その結果、中性子の無駄な吸収を防1トす/)ことh
;できる。
In Figure 3, by inserting the solid line graph to the negative side of the insertion depth, in order to take advantage of the neutron 1j4', t'ik absorption reduction effect, the control rod effective section 2 is changed to the fuel effective section. 4
Than which culm Sho's t + t no shaku - 111, 1 after Bayoi! 'j'Th'E limit Vf-value is obtained. According to Figure 3, this t(z scaling limit value is -15%
It can be seen that the hardness (corresponding to the insertion depth) is shortened. Is this 1゛] thinking-ko, υ1jI(!I
Target f! , as 1 and 11 of Gao Ke I breeder reactor, fuel Ij'no part 4 f-j sa l 00 an % upper ¥XB
Assuming a core of 1it-+ direction blunt foot 5, the length of the control rod effective section 2 will be approximately 15 m, that is, approximately 15 m or more than the length of the -L section blanket, and -r' will also be approximately It can be seen that this does not lead to further improvement in the effect of reducing wasted neutron absorption. That is,
In order to achieve the effect of reducing wasted neutron absorption, control rod effective section 2
is the granket 5 in the direction of the upper axis lj compared to the fuel effective part 4.
It can be seen that it is sufficient to shorten the length by a length smaller than lA of zero intensity 1. Furthermore, although volatile substances generated by nuclear fission are stored, the sprenano 7 is placed on one side of the fuel effective part 4. In a reactor core in which the upper part uses Szolenum type fuel rods, the entire effective fuel section 4 is located lower than in the case of Figures 1 and 2, so there is a restriction on the drive stroke of the control rods. Generally, it has been tried that there is a tendency for the control f+QI rod effective part to be slightly reduced by −+11 in the fully withdrawn state, but according to the present invention, the control f+QI rod effective part is The lower end of the neutron effective part 4 can be placed at the upper end of the effective part 4 than the lower end of the effective part 4, and as a result, wasteful absorption of neutrons can be prevented.
;can.

さらに、制御棒心・)11部2の短尺化1fi、放射性
廃昨物々jL理を減らす効甲もあることは占うまでもな
い。
Furthermore, it goes without saying that shortening the length of the control rod core (11 part 2) will also have the effect of reducing the amount of radioactive waste.

μ上説明l、2/こように、本発明によれば、高速増殖
炉においでi[V!常・軍転時の中PI: r−無駄吸
IIyが低減されるの−で”、代表的原子炉について9
〜10日の原子炉運転ト1数6+r、 1%をはかるこ
とが可能であって、これはl (10、−fj kW級
の原子炉では年11113 Of、α〜100億円の増
収人を0]゛能にするものであり、また□iti転[]
数を延団り、 ;’zい場合には核分裂性物゛efの装
荷11を減少さ1セることがでべるという(11点をも
たらすものである。さらに、4発明は)々Q、を性l晃
Jド′物Mの低減を可能にするという効果もある。
μ Explanation l, 2/Thus, according to the present invention, in a fast breeder reactor, i[V! Medium PI at the time of normal/military transition: ``Because wasteful intake IIy is reduced'', about typical nuclear reactors 9
~10 days of reactor operation 16 + r, 1%, which is l (10, -fj For a kW class reactor, 11113 Of, α ~ 10 billion yen increase in income. [0]
It is said that if the number is increased, it is possible to reduce the loading of fissile material ef by 1 (11 points).Furthermore, the 4 inventions are , it also has the effect of making it possible to reduce the amount of physical damage.

【図面の簡単な説明】[Brief explanation of drawings]

第1図1j % 7x)’:来の高速噌殖炉に粋ける:
ttll i’fll財ケと・l?、!y i:111
を合体との長さ及び位置関係をkわす担′tよ図、第2
図に1、+発明の実1KIi例における制(、Iil欅
と・1伊料1p合体との長さ及び付II′h関係全示″
J−it′t、急回、s″■s 3図は従・K例−1?
よび・ト発明の(こ施i4;lでの制fil伜の111
人に伴なうjlil、制御棒の制量Ij■能反応11(
−の相りzt変化を示すグラフである。 1・・・燃料イ4キ合体、   2・・・制預(I棒有
効部、3・・・燃料棒、    4・・・燃料有効部、
5・・・L部軸方向ブランク゛ット、 6・・・下部’l’lll力向プランケ、ト、7・・・
がスプレナノ2、 8・・・制仰棒′セ内管。 t・ 、I 代pH人  ト タ・ 小 ++  □°、′1−1刀 第2図
Figure 1 1j % 7x)': Useful for the next high-speed soybean fermenter:
ttll i'flll Zaikato・l? ,! yi:111
Figure 2 shows the length and positional relationship between the two parts.
Figure 1 shows the system in the actual 1KIi example of the invention (the length of the combination of Iil Keyaki and 1Iryo 1p, and the complete relationship of II'h).
J-it't, sudden turn, s''■s Figure 3 is subordinate/K example-1?
111 of the invention (this i4;
jlil accompanying people, control rod control Ij ■ ability reaction 11 (
It is a graph showing a change in the ratio zt of -. 1... Combination of 4 fuel rods, 2... Deposit (I rod effective part, 3... Fuel rod, 4... Fuel effective part,
5...L section axial blank cut, 6...Lower 'l'lll force direction blanket, 7...
are Splenano 2, 8... control rod' inner tube. t・,I generation pH person Tota・small ++ □°,'1-1 sword 2nd figure

Claims (1)

【特許請求の範囲】 1、 反応度の制御のだめに中性子吸収材を内蔵した制
御棒を用いる高速増殖炉用制御棒装置において、制御棒
に内蔵された中性子吸収材で与えられる制御棒有効部の
長さを燃料棒に内蔵された核分裂性物質で与えられる燃
料有効部の長さよりパ5短くし、目、つ制御棒の完全引
抜状態において−f二Nc。 制御棒有効部の下端を上記撚t)有効部の」一端よりも
十ノjに位置せしめるようにしたことを特徴とする高速
増殖炉用制御棒装置。 2、燃料有効部の長さと制御棒有効部の長さの差が上記
燃料廂効部の上部に設けられだ」二部軸方向ブランケッ
トの長さの2分の1よりも小さいことを特徴とする唱゛
¥[請求の範囲第1項記載の高速増殖炉用制御枠装(べ
[Claims] 1. In a control rod device for a fast breeder reactor that uses a control rod with a built-in neutron absorber for reactivity control, the effective part of the control rod provided by the neutron absorber built into the control rod is The length is made 5 shorter than the length of the effective fuel section given by the fissile material contained in the fuel rod, and when the control rod is fully withdrawn, -f2Nc. A control rod device for a fast breeder reactor, characterized in that the lower end of the control rod effective section is located at a distance from one end of the twisted effective section. 2. The difference between the length of the effective fuel part and the length of the control rod effective part is less than half the length of the two-part axial blanket provided in the upper part of the fuel effective part. [The control frame for fast breeder reactor according to claim 1]
JP57155040A 1982-09-06 1982-09-06 Control rod device for fast breeder Granted JPS5943384A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP57155040A JPS5943384A (en) 1982-09-06 1982-09-06 Control rod device for fast breeder

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP57155040A JPS5943384A (en) 1982-09-06 1982-09-06 Control rod device for fast breeder

Publications (2)

Publication Number Publication Date
JPS5943384A true JPS5943384A (en) 1984-03-10
JPH0350233B2 JPH0350233B2 (en) 1991-08-01

Family

ID=15597351

Family Applications (1)

Application Number Title Priority Date Filing Date
JP57155040A Granted JPS5943384A (en) 1982-09-06 1982-09-06 Control rod device for fast breeder

Country Status (1)

Country Link
JP (1) JPS5943384A (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4762672A (en) * 1984-10-12 1988-08-09 Hitachi, Ltd. Fast breeder reactor

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4762672A (en) * 1984-10-12 1988-08-09 Hitachi, Ltd. Fast breeder reactor

Also Published As

Publication number Publication date
JPH0350233B2 (en) 1991-08-01

Similar Documents

Publication Publication Date Title
Uchikawa et al. Conceptual design of innovative water reactor for flexible fuel cycle (FLWR) and its recycle characteristics
JPS5943384A (en) Control rod device for fast breeder
JPS5819592A (en) Fast breeder
JP4098002B2 (en) Fuel assemblies and reactor cores
JPS60188880A (en) Fuel aggregate for nuclear reactor
JPH0588439B2 (en)
JP3085715B2 (en) Reactor operation method
JPS62200290A (en) Control rod for nuclear reactor
JPH0675077A (en) Fuel assembly for nuclear reactor
JPS6082885A (en) Control rod for nuclear reactor
JPS6151275B2 (en)
JPS63127190A (en) Nuclear reactor fuel aggregate
JP4308940B2 (en) Fuel assembly
Nishimura 3.2 Advances of reactor core and fuel assembly 3.2. 1 High burnup fuel design
JP3167771B2 (en) Reactor and fuel assemblies
JP2972255B2 (en) Reactor
JP2509625B2 (en) Core structure of fast breeder reactor
JPS59116578A (en) Reactor
JPS6186676A (en) Hollow control rod nuclear reactor
JP2002350579A (en) Fuel assembly
Yamashita et al. Development of a high-conversion boiling water reactor
JPH06331766A (en) Fuel assembly
JPS63149588A (en) Fuel aggregate for nuclear reactor
Chien et al. Utilization of heavy elements in thermal and epithermal reactors
JPS6258193A (en) Operation control rod for nuclear reactor