JPS6027897A - Method of controlling quantity of neutron absorbed - Google Patents

Method of controlling quantity of neutron absorbed

Info

Publication number
JPS6027897A
JPS6027897A JP58137145A JP13714583A JPS6027897A JP S6027897 A JPS6027897 A JP S6027897A JP 58137145 A JP58137145 A JP 58137145A JP 13714583 A JP13714583 A JP 13714583A JP S6027897 A JPS6027897 A JP S6027897A
Authority
JP
Japan
Prior art keywords
neutron
hydrogen
absorbing material
neutron absorption
hydrogenation rate
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
JP58137145A
Other languages
Japanese (ja)
Inventor
芳明 鈴木
小玉 強
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.)
Nippon Steel Corp
Original Assignee
Sumitomo Metal Industries 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 Sumitomo Metal Industries Ltd filed Critical Sumitomo Metal Industries Ltd
Priority to JP58137145A priority Critical patent/JPS6027897A/en
Publication of JPS6027897A publication Critical patent/JPS6027897A/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

  • Analysing Materials By The Use Of Radiation (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】 この発明は、中性子吸収材の中性子吸収量を調節するこ
とを可能ならしめる方法に関する。
DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a method that makes it possible to adjust the amount of neutron absorption of a neutron absorber.

中性子吸収材料は、中性子との相互作用により、弾性散
乱、非弾性散乱、(n、γ)、(u、p)、(”+α)
反応等種々の反応をおこし、その結果として中性子減速
、吸収するもので、用途としては、原子炉の制御棒や安
全棒、研究用の中性子束調整機の遮蔽材などがめる。
Neutron absorbing materials can cause elastic scattering, inelastic scattering, (n, γ), (u, p), (''+α) due to interaction with neutrons.
It causes various reactions such as reactions, and as a result, slows down and absorbs neutrons. Applications include control rods and safety rods in nuclear reactors, and shielding materials for neutron flux regulators for research.

中性子吸収材料としては現在、Ag−In−Cd合金1
BaC,Ta、 EllxOv 、 ホを素鋼、 Cd
、203. H3EC)y 。
Currently, Ag-In-Cd alloy 1 is used as a neutron absorbing material.
BaC, Ta, EllxOv, raw steel, Cd
, 203. H3EC)y.

ホウケイ酸ガフヌ、ポラール、IaFタイル等、多くの
ものが知られている。これらは何れも、構成元素それ自
体が中性子吸収断面積或いは中性子散乱断面積の大@な
もの、若しくはそれらの化合物や合金からなるものであ
る。
Many are known, such as borosilicate gafnu, polar, and IaF tiles. In all of these, the constituent elements themselves have a large neutron absorption cross section or neutron scattering cross section, or they are composed of compounds or alloys thereof.

さてかかる材料においてその中性子吸収特性は、各材料
に固有のものとして一定なわけであり、したがって実際
使用に当っては機器設計の段階で、予めその点を考慮に
入れて構造設計を行うようにすることが必要であり、こ
のことは場合によってはシヌデム全体の構成にまで大き
く影響してくることさえある。何れにしても、中性子吸
収特性が固定されたものであるということは、設計上大
きな制約となるものである。またとくに、原子炉の制御
棒では、使用中稼動条件に応じて中性子吸収効率を変更
することが必要とされるが、このような場合、材料の中
性子吸収特性が一定では、制御棒の位置移動等、物理的
な方法で対処するしかなく、このような方法は中性子分
布の不均一化を招く等の問題がある。
Now, the neutron absorption characteristics of such materials are unique and constant for each material, so in actual use, it is necessary to take this into consideration in the structural design at the equipment design stage. It is necessary to do so, and in some cases, this may even have a significant impact on the overall composition of the synudem. In any case, the fact that the neutron absorption characteristics are fixed is a major constraint in terms of design. In particular, it is necessary to change the neutron absorption efficiency of control rods in nuclear reactors depending on the operating conditions during use. The only way to deal with this problem is to use physical methods, and such methods have problems such as non-uniformity of neutron distribution.

本発明は、このような問題解決の有効策として、中性子
吸収材料の中性子吸収特性を可逆的かつ連続的に変更、
制御することを可能ならしめる方法を提供しようとする
ものである。
As an effective measure to solve such problems, the present invention aims to reversibly and continuously change the neutron absorption properties of neutron absorption materials.
The aim is to provide a method that allows for control.

すなわち本発明は、中性子吸収材として、水素と可逆的
に反応する中性子吸収材料を用い、これを水素雰囲気中
に置きその雰囲気水素の圧力、温度の何れか一方または
双方を変化させることにより、前記中性子吸収材の水素
化率を調節してその中性子吸収量を制御することを特徴
とする中性子吸収量の制御方法を要旨とする。
That is, the present invention uses a neutron absorbing material that reacts reversibly with hydrogen as a neutron absorbing material, and by placing it in a hydrogen atmosphere and changing either or both of the pressure and temperature of the hydrogen atmosphere, The gist of this invention is a method for controlling the amount of neutron absorption, which is characterized by controlling the amount of neutron absorption by adjusting the hydrogenation rate of a neutron absorbing material.

水素と可逆的に反応し得、しかも大きな中性子吸収断面
積をもつ金属に、HfおよびHf合金(以下、これらの
総称として「Hf」を使う)がある。
Metals that can reversibly react with hydrogen and have a large neutron absorption cross section include Hf and Hf alloys (hereinafter referred to as "Hf").

すなわちHfのパウダーは、水素に接触させると反応し
HfHr (1<x<2 )の形のハフニウム水素化物
を形成する。そしてこの場合、Hf水素化の比率は、接
触δせる水素の圧力、温度に依存し、しかもこれら2つ
の条件の設定変えによって可逆的に変化δせ得るもので
ある。第1図は、Hfの水素化率(水素含有M @/ 
Hf i (IV) (atom rati−o )で
示す)と雰囲気水素の圧力(p)の関係についてその傾
向を概念的に示したものであるが、同図に示すような関
係でHfの水素化率は水素圧力史)によって可逆的に変
化するものである。この水素化率は、接触水素の温度条
件の変更によっても、類似の変化傾向を示す。
That is, when the Hf powder is brought into contact with hydrogen, it reacts to form hafnium hydride of the form HfHr (1<x<2). In this case, the Hf hydrogenation ratio depends on the pressure and temperature of the hydrogen brought into contact δ, and can be reversibly changed by changing the settings of these two conditions. Figure 1 shows the hydrogenation rate of Hf (hydrogen content M @/
This diagram conceptually shows the tendency of the relationship between Hf i (IV) (denoted as atom ratio-o) and the atmospheric hydrogen pressure (p). The rate changes reversibly depending on the hydrogen pressure history). This hydrogenation rate shows a similar tendency to change even when the temperature conditions of catalytic hydrogen are changed.

一方、上記水素は、いわゆる弾性散乱(中性子を減速さ
せる反応の1種)に関する断面積が大きいことはよく知
られるところで65、したがって上記Hfパウダーは前
記水素化によって中性子減速能を保有する水素化物とな
り、そしてこの水素化物のもつ中性子減速能の太きδは
その水素化率に依存するものである。このようなことか
ら、Hfパウダーは、その水素化率によって中性子吸収
断面漬け)が変化するものである。第2図は、Hfの水
素化率<HAA)とその中性子吸収断面積(財))との
関係を概念的に示したもので、同図に示すように前記σ
は水素化率に対応して、](f単独での吸収断面積(σ
/〕からHf水素化物の吸収断面積(σコ)までの17
1]で連続的に変化するものである。
On the other hand, it is well known that the above hydrogen has a large cross section regarding so-called elastic scattering (a type of reaction that slows down neutrons)65, so the above Hf powder becomes a hydride that has neutron moderation ability through the hydrogenation. , and the thick δ of the neutron moderating ability of this hydride depends on its hydrogenation rate. For this reason, the neutron absorption cross section of Hf powder changes depending on its hydrogenation rate. Figure 2 conceptually shows the relationship between the hydrogenation rate of Hf <HAA) and its neutron absorption cross section (product).
corresponds to the hydrogenation rate, ](f alone absorption cross section (σ
/] to the absorption cross section of Hf hydride (σ) 17
1] and changes continuously.

したがって前記本発明の方法によれば、中性子吸収材料
の水素化率の調節によってその中性子吸収断面積、云い
換えれば中性子吸収量を可逆的かつ連続的に制御するこ
とができるものである。
Therefore, according to the method of the present invention, the neutron absorption cross section, or in other words, the amount of neutron absorption, can be reversibly and continuously controlled by adjusting the hydrogenation rate of the neutron absorbing material.

本発明の方法を実施するための中性子吸収材の水素化装
置の概念図を第1図に示す。同図において、(1)は中
性子吸収材としてのHfパウダーで、ステンレス系フィ
ルターからなる内筒C21内に充填、封入でれている。
FIG. 1 shows a conceptual diagram of a neutron absorbing material hydrogenation apparatus for carrying out the method of the present invention. In the figure, (1) is Hf powder as a neutron absorbing material, which is filled and enclosed in an inner cylinder C21 made of a stainless steel filter.

〔3〕はHfパウダーを封入した内筒(2)の外側に設
けた外筒で、内筒(2)との間の空間には水素が満たδ
れている。この外筒の一端には管(4)が付設されてお
り、これを通じて内・外筒間に水素を送り或いは回収す
ることによシ、内部水素の圧力を調節するようになって
いる。また、前記内筒(2)の外周には、熱交換器(5
)が巻設されており、これにより内・外筒間の水素温度
を調節できる構造になっている。
[3] is an outer cylinder installed outside the inner cylinder (2) containing Hf powder, and the space between it and the inner cylinder (2) is filled with hydrogen.
It is. A pipe (4) is attached to one end of the outer cylinder, through which hydrogen is sent or recovered between the inner and outer cylinders, thereby adjusting the internal hydrogen pressure. Further, a heat exchanger (5) is provided on the outer periphery of the inner cylinder (2).
) is wound around it, which allows the hydrogen temperature between the inner and outer cylinders to be adjusted.

本発明の方法は、具体的には、例えばこのような装置に
おいて、中性子吸収材(1)K発泡金属からなる内筒(
2〕を通して水素を接触させてその水素化を図る。そし
て、内・外筒(2)(3)間の水素の圧力、温度を、管
(4)による水素の給排と熱交換器(5)の温度調節に
よって変化させ、前記中性子吸収材(1)の水素化率を
調節することによυ、その中性子吸収量の制御を行うも
のである。
Specifically, the method of the present invention can be applied to, for example, an inner cylinder made of a neutron absorbing material (1) K foam metal in such an apparatus.
2] through which hydrogen is brought into contact and hydrogenated. Then, the pressure and temperature of hydrogen between the inner and outer cylinders (2) and (3) are changed by supplying and discharging hydrogen through the pipe (4) and adjusting the temperature of the heat exchanger (5), and the neutron absorbing material (1) ) The amount of neutron absorption is controlled by adjusting the hydrogenation rate of υ.

なお、Hf (単体)もしくは各種のHf合金パウダー
の水素化率とその水素化物の中性子吸収断面積が、水素
圧力、更にはその温度条件によって変化することについ
て、本発明者らは実験にて確認済みである。
The inventors have confirmed through experiments that the hydrogenation rate of Hf (single substance) or various Hf alloy powders and the neutron absorption cross section of the hydride change depending on the hydrogen pressure and temperature conditions. It has been completed.

以上の説明から明らかなように本発明の中性子吸収量の
制御方法は中性子吸収材の中性子吸収量を可成り広い巾
で自在に制御することが可能であり、このことは中性子
吸収材を使用する各種システムの設計上の制約の解消を
通してその合理化の効果をもたらすものであシ、またと
ぐに原子炉の制御棒のように使用中中性子吸収効率を変
化させ′る必要があるようなものに適用すれば、従来の
ように中性子吸収材の移動等で対処する必要がなくなフ
、それに伴う問題が一掃でれるメリットが得られるもの
である。
As is clear from the above explanation, the method for controlling the neutron absorption amount of the present invention allows the neutron absorption amount of the neutron absorbing material to be freely controlled over a fairly wide range. It has the effect of rationalizing various systems by eliminating design constraints, and will soon be applied to items such as control rods in nuclear reactors that require changes in neutron absorption efficiency during use. This eliminates the need to deal with the movement of the neutron absorber as in the past, and provides the advantage of eliminating problems associated with this.

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

第1図はIfパウダーに接触する水素の圧力とその水素
化率の関係、第2図は同じく水素化率とその中性子吸収
断面積の関係、をそれぞれ示す線図である。第3図は本
発明の中性子吸収量の制御方法を火施するための装置の
一例を概念的に示す縦断模式図、である。 図中、1:中性子吸収材、2:内筒、3:外筒、4:管
、5:熱交換器 第 1 図 第2図 Hfの水素4ヒ卑 H/M 第 3 図
FIG. 1 is a diagram showing the relationship between the pressure of hydrogen in contact with the If powder and its hydrogenation rate, and FIG. 2 is a diagram showing the relationship between the hydrogenation rate and its neutron absorption cross section. FIG. 3 is a schematic longitudinal sectional view conceptually showing an example of an apparatus for applying the method of controlling the amount of neutron absorption according to the present invention. In the figure, 1: Neutron absorber, 2: Inner cylinder, 3: Outer cylinder, 4: Tube, 5: Heat exchanger.

Claims (1)

【特許請求の範囲】[Claims] (1)中性子吸収材として、水素と可逆反応する中性子
吸収材料を用い、これを水素算囲気中に置いてその雰囲
気水素の圧力、温度の何れか一方または双方を変化1せ
ることによシ、前記中性子吸収材の水素化率を調節して
その中性子吸収量を制御することを特徴とする中性子吸
収量の制御方法。
(1) By using a neutron absorbing material that reversibly reacts with hydrogen as a neutron absorbing material, placing it in a hydrogen atmosphere, and changing either or both of the pressure and temperature of the hydrogen atmosphere, A method for controlling the amount of neutron absorption, characterized in that the amount of neutron absorption is controlled by adjusting the hydrogenation rate of the neutron absorbing material.
JP58137145A 1983-07-26 1983-07-26 Method of controlling quantity of neutron absorbed Pending JPS6027897A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP58137145A JPS6027897A (en) 1983-07-26 1983-07-26 Method of controlling quantity of neutron absorbed

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP58137145A JPS6027897A (en) 1983-07-26 1983-07-26 Method of controlling quantity of neutron absorbed

Publications (1)

Publication Number Publication Date
JPS6027897A true JPS6027897A (en) 1985-02-12

Family

ID=15191864

Family Applications (1)

Application Number Title Priority Date Filing Date
JP58137145A Pending JPS6027897A (en) 1983-07-26 1983-07-26 Method of controlling quantity of neutron absorbed

Country Status (1)

Country Link
JP (1) JPS6027897A (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2013525809A (en) * 2010-05-07 2013-06-20 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 Control rods for light water reactors

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2013525809A (en) * 2010-05-07 2013-06-20 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 Control rods for light water reactors
US9230696B2 (en) 2010-05-07 2016-01-05 Westinghouse Electric Sweden Ab Control rod for a nuclear power light water reactor
EP2567383B1 (en) * 2010-05-07 2016-03-30 Westinghouse Electric Sweden AB Control rod for a nuclear power light water reactor

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