JPS59163591A - Control rod for light water reactor - Google Patents

Control rod for light water reactor

Info

Publication number
JPS59163591A
JPS59163591A JP58037816A JP3781683A JPS59163591A JP S59163591 A JPS59163591 A JP S59163591A JP 58037816 A JP58037816 A JP 58037816A JP 3781683 A JP3781683 A JP 3781683A JP S59163591 A JPS59163591 A JP S59163591A
Authority
JP
Japan
Prior art keywords
control rod
neutron
light water
sheath
water reactor
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
Application number
JP58037816A
Other languages
Japanese (ja)
Inventor
章 西村
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 JP58037816A priority Critical patent/JPS59163591A/en
Publication of JPS59163591A publication Critical patent/JPS59163591A/en
Pending 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

Landscapes

  • Physical Or Chemical Processes And Apparatus (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】 本発明は軽水原子炉、特に沸騰水型原子炉に適する制御
棒に関する。
DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a control rod suitable for light water nuclear reactors, particularly boiling water reactors.

この釉の制御棒の一従来例は、全体斜視図である第1 
(!!J及び部分横断面図である第2図VCボすように
、中央のタイ、r′]ツド1に十字形に固着したシース
2内に中性子吸収材である炭化ボロシ(B4C)の粉末
を充填した多数の中性子吸収管4を収納したものであり
、これを炉心に挿入することにより中性子を吸収して原
子炉の出力制御を行うものである。5はハルドルである
。このような制御棒は、炭化ボロル(B4C)が中性子
を吸収するとボロル(B)がヘリウム(He)とリチウ
ム(Ll)とに変って中性子吸収能力がなくなること、
及び炭化ボ[1シ(B4C)内にたまったヘリウム(H
e)により中性子吸収管の機憧的寿6が制限されること
等の原因で人命が比較的短いという欠点がある。
One conventional example of this glazed control rod is the first example which is an overall perspective view.
(!! J and Fig. 2 VC, which is a partial cross-sectional view, shows the center tie, r') Inside the sheath 2 fixed to the joint 1 in a cross shape, carbide borosilicate (B4C), which is a neutron absorbing material, is placed. It houses a large number of neutron absorption tubes 4 filled with powder, and when inserted into the reactor core, absorbs neutrons and controls the output of the reactor. 5 is a haldle. When the control rod absorbs neutrons, borol carbide (B4C) changes to helium (He) and lithium (Ll) and loses its neutron absorption ability.
and helium (H
There is a disadvantage that human life is relatively short due to the limitation of the expected lifespan 6 of the neutron absorption tube due to e).

他方、中性子を吸収してもγ線を放出するだけで中性子
吸収能力を失わずヘリウム(He)も発生しない(n+
1)反応型の中性子吸収材を用いた制御棒も従米知られ
ているが、そのような制御棒は一般に重量が〕1(いと
いう欠潰がある。
On the other hand, even if it absorbs neutrons, it only emits gamma rays, does not lose its neutron absorption ability, and does not generate helium (He) (n+
1) Control rods using reactive neutron absorbers are also known, but such control rods generally have a disadvantage in that they weigh only 1.

本発明の目的は、このような従来の制御棒の欠点に鑑み
、(rt+γ)反応型の中性子吸収材の使用により長寿
命化を図りながら、しかも@量化が可能であり、かつ制
御能力の調整の容易な軽水原子炉用制御棒を提供するこ
と[6る。
In view of these shortcomings of conventional control rods, the purpose of the present invention is to extend the life of the control rod by using (rt+γ) reaction type neutron absorbing material, while also being able to be quantified and to adjust the control ability. To provide a control rod for a light water reactor that is easy to use [6].

本発明の軽水原子炉用制御棒の詩歌け、シース内に繊維
状又はりポジ状の(貼γ)反応型の中性子吸収材を内蔵
した点にある。
The beauty of the control rod for a light water reactor of the present invention is that it incorporates a fibrous or positive (gamma) reactive neutron absorbing material within the sheath.

以下−1本発明による制御棒の一実施例を説明する。こ
の制@1棒は第1図に示した従来の制側J棒と比較する
と、タイロツド1、シース2、ハシドル5等の形状は同
じであるが、シース2の内部には、第3図に示すように
、大きい中性子吸収能力を釣つ丁記の材料を棒−維1ツ
ク又(4リホL状とした中性子吸収材3が入れである。
Below-1, one embodiment of the control rod according to the present invention will be described. This control @1 rod has the same shape as the tie rod 1, sheath 2, hashidle 5, etc. when compared to the conventional control side J rod shown in Fig. 1, but inside the sheath 2, as shown in Fig. 3. As shown, a neutron absorbing material 3 made of the above-mentioned material having a large neutron absorption capacity is made into a rod-fiber or L shape.

さらに冷却幼果と中性子吸収能力を一后向上させるため
に、シース2に複数の穴をあけて中1住子弦迷拐(軽水
)が辿るようにしである。但し穴のない密封したシース
の場合には、シースのh都に減速材として炭素を混在さ
せてもよい。
Furthermore, in order to further improve the cooling ability of young fruits and neutron absorption, a plurality of holes are made in the sheath 2 so that light water can be passed through the sheath 2. However, in the case of a sealed sheath without holes, carbon may be mixed as a moderator in the sheath.

上記の中性子吸収能力を持つ材料としては、ハフニウム
(Hf)、カドミウム(cd)、又は立沢・イシがラム
・フ]ド巳つム(Ag・工n−cd )合釡等の如@’
(n+1)反応を起す金属材料が適している。
Examples of materials that have the above-mentioned neutron absorption ability include hafnium (Hf), cadmium (CD), and Tatsuzawa-Ishi's Lamb Fudotsumu (Ag/N-CD) alloy.
A metal material that causes an (n+1) reaction is suitable.

これらの金属材料を上記のように繊維状又はリホシ状に
した理由は、 (aJ  表@槓の増大(てよる中性子吸収能力の向上
、(b)  中性子減速材(水又は炭素等)との均一な
混在による中性子吸収能力の同上、 (cl  減球材(水の場合)による伶却効釆の増大、
(d)  中性子吸収材の体積率の答易な調榮・(el
  Hg量化 等を図ることにaる。
The reasons for making these metal materials into fibrous or rehoshi-like shapes as mentioned above are (aJ Table @ Increased neutron absorption capacity (b) Uniformity with neutron moderators (water, carbon, etc.) Same as above for the neutron absorption capacity due to the mixture of
(d) Easy adjustment of the volume fraction of the neutron absorber (el
The aim is to quantify Hg, etc.

第3図にボした実施例に2いてシース2とタイ口・ソド
1とで囲−i:n−た領域に中・1十子吸収舵力を有す
る材料としてハフニウムを繊維状又はリボル状にしてな
る中性子吸収材3f収容し敷速拐(水)全通した場合に
関し、この(n+1)反応型のハフニウムからなる中1
1.子吸収材3がシース2とタイロツド1とで1外まれ
た体槓甲に占る割合(体積率)と制御棒反応度相対II
I+]値との関係を第4図に示す。図中の制御棒反応度
相対価値は同じ外形寸法を持つ前記従来の制御棒の反応
度価値を基準(−1,0)としたときの値である0この
図から、本実施例では中性子吸収材が占る体積率が約1
0チ以上あれは従来の制御棒と同程度以上の制御棒反応
度価値を有すること及び従来の制御棒の反応度価値の9
0チ1でを許容するとすれば上記の中性子吸収材の体積
率は5饅以上であればよいことがわかる。
In the example 2 shown in Fig. 3, hafnium is used in the form of fibers or revolvers as a material having a steering force capable of absorbing the middle and tenth elements in the area surrounded by the sheath 2 and the tie opening/socket 1. Regarding the case where 3f of neutron absorbing material made of
1. Ratio (volume ratio) of the child absorber 3 to the body shell removed by the sheath 2 and tie rod 1 and control rod reactivity relative II
FIG. 4 shows the relationship with the I+] value. The relative reactivity value of the control rod in the figure is the value when the reactivity value of the conventional control rod with the same external dimensions is used as the standard (-1, 0).From this figure, it can be seen that in this example, neutron absorption The volume ratio occupied by the material is approximately 1
0chi or more means that the control rod has a reactivity value equal to or higher than that of a conventional control rod, and the reactivity value of the conventional control rod is 9
It can be seen that if 0 x 1 is allowed, the volume fraction of the above neutron absorbing material should be 5 or more.

本発明の制御棒は、上記実施例の他しで、ii前記の如
き中性子吸収材を従来の制御棒と同様な多数の中性子吸
収材に内封しこれらをシースで囲んだ構成の実施例もL
:lJ耗である。この場合は水による減速効果が減るの
・たけ中性子吸収材の体積率を大きくする必要がある。
In addition to the above-described embodiments, the control rod of the present invention also includes an embodiment in which ii) the above-mentioned neutron absorbers are enclosed in a large number of neutron absorbers similar to those of conventional control rods, and these are surrounded by a sheath. L
:lJ wear. In this case, it is necessary to increase the volume fraction of the neutron absorbing material because the moderating effect of water is reduced.

不発明の制伊1棒では、先に挙げたへワニ[)Δ等の中
性子吸収材は大きな中性子吸収能力を有する同位体が存
在するため、炭化ボロ、z B4Cとは異り中性子を一
度吸収しても中性子1ルー収能力が下らずに持続し、さ
らに(n+1)反応材であるためヘリウムも発生しない
ので、従来の1llj ’AI棒より長い寿命が期待で
きると共に、中性子吸収材の辰面績が犬合いので中性子
吸収能力が向上し、中性子吸収材の占める体積率が小さ
くて厖従米の制御棒と同等以上の制御能力を持たーぎる
ことかでき、軽量化が容易である。
In the uninvented 1 stick, neutron absorbing materials such as Hewani[)Δ, which were mentioned earlier, have isotopes that have a large neutron absorption ability, so unlike carbide borosilicate and z B4C, neutron absorbers absorb neutrons once. However, the neutron 1 ru capacity remains unchanged even when the rod is used, and since it is an (n+1) reactive material, it does not generate helium. Since the performance is comparable, the neutron absorption capacity is improved, and the volume ratio occupied by the neutron absorbing material is small, so it can have a control capacity equal to or higher than that of the control rod of the control rod, and it is easy to reduce the weight.

また本発明の制御棒では中性子吸収材のf度(体積率)
を容易に変えることができる。通常、制御棒の先端部で
は中は子束が高く中性子吸収材が大きいので、長寿命化
を図るには制御棒先端部における中性子1技収利の体積
率を上げることが有効であり、逆に、fli制御作制御
部先端部する燃料の出力の急激な変化をチー2日するV
C(・はこの部分の中性子吸収材の体モに率を小さくす
るのがよい。本発明1cよれば、このような必なVC比
、じ中性子吸収材の体積率を変えることが容易であるか
ら制御能力を容易に稠榮し得る利点がある。
In addition, in the control rod of the present invention, the f degree (volume fraction) of the neutron absorbing material is
can be easily changed. Normally, the tip of a control rod has a high flux of neutrons and a large amount of neutron absorbing material inside, so increasing the volume ratio of neutrons at the tip of the control rod is effective in extending its life. At the same time, a sudden change in the output of the fuel at the tip of the fli control operation control section is detected.
It is preferable to reduce the body ratio of the neutron absorbing material in this part.According to the present invention 1c, it is easy to change the necessary VC ratio and the volume fraction of the neutron absorbing material. There is an advantage that the control ability can be easily increased from

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

第1図はに米の制御棒の全体斜視的、第2図は第1図の
制御棒の部分横断面図、第3図は本発明の制御棒の実施
例をボす6μ分、紀4図は上記実施例における中性子吸
収材の占る体積率と制御棒反応度相対価値との胸係を示
す図である。 ■・・・タイロッド   2・・・シース3・・中・、
・十子吸′収材  4・・・中性パ子吸収管5・・・ハ
シドル −−−− 代エラP人   本  多  小 半 箱2図 第31ゾ
Figure 1 is a perspective view of the entire control rod, Figure 2 is a partial cross-sectional view of the control rod in Figure 1, and Figure 3 is an embodiment of the control rod of the present invention. The figure is a diagram showing the relationship between the volume fraction occupied by the neutron absorbing material and the relative value of control rod reactivity in the above embodiment. ■...Tie rod 2...Sheath 3...Medium...
・Jyuko absorption material 4...Neutral Pako absorption tube 5...Hashidor---Yoero P person Book Large Small Half box 2 Figure 31 Zo

Claims (1)

【特許請求の範囲】 l シース内に中性子吸収能力の大きい(n+1)反応
型の材料で作られた繊維状またはりホシ状の中性子吸収
材を内蔵したことを特徴とする軽水原子炉用制御棒。 2 シース内に前記の中性子吸収材と共て、中性子吸収
管としての軽水または炭素を混在せしめたことを特徴と
する特許請求の範囲第1項記載の軽水原子炉用制御棒。
[Scope of Claims] l. A control rod for a light water reactor, characterized in that a fibrous or hob-like neutron absorbing material made of an (n+1) reaction type material with a large neutron absorption capacity is incorporated in the sheath. . 2. The control rod for a light water reactor according to claim 1, characterized in that light water or carbon as a neutron absorption tube is mixed in the sheath together with the neutron absorption material.
JP58037816A 1983-03-08 1983-03-08 Control rod for light water reactor Pending JPS59163591A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP58037816A JPS59163591A (en) 1983-03-08 1983-03-08 Control rod for light water reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP58037816A JPS59163591A (en) 1983-03-08 1983-03-08 Control rod for light water reactor

Publications (1)

Publication Number Publication Date
JPS59163591A true JPS59163591A (en) 1984-09-14

Family

ID=12508044

Family Applications (1)

Application Number Title Priority Date Filing Date
JP58037816A Pending JPS59163591A (en) 1983-03-08 1983-03-08 Control rod for light water reactor

Country Status (1)

Country Link
JP (1) JPS59163591A (en)

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPH0275996A (en) * 1988-07-28 1990-03-15 Europ De Zirconium Cezus:Co Neutron absorption element made of metal and manufacture of said element
JP2009168207A (en) * 2008-01-18 2009-07-30 Kayaba Ind Co Ltd Front fork
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

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPH0275996A (en) * 1988-07-28 1990-03-15 Europ De Zirconium Cezus:Co Neutron absorption element made of metal and manufacture of said element
JP2009168207A (en) * 2008-01-18 2009-07-30 Kayaba Ind Co Ltd Front fork
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

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