JPH10226848A - Neutron absorbing alloy - Google Patents

Neutron absorbing alloy

Info

Publication number
JPH10226848A
JPH10226848A JP9052309A JP5230997A JPH10226848A JP H10226848 A JPH10226848 A JP H10226848A JP 9052309 A JP9052309 A JP 9052309A JP 5230997 A JP5230997 A JP 5230997A JP H10226848 A JPH10226848 A JP H10226848A
Authority
JP
Japan
Prior art keywords
stainless steel
boron
neutron absorbing
neutron
alloy
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Withdrawn
Application number
JP9052309A
Other languages
Japanese (ja)
Inventor
Masao Toba
正男 鳥羽
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.)
Nuclear Fuel Industries Ltd
Original Assignee
Nuclear Fuel 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 Nuclear Fuel Industries Ltd filed Critical Nuclear Fuel Industries Ltd
Priority to JP9052309A priority Critical patent/JPH10226848A/en
Publication of JPH10226848A publication Critical patent/JPH10226848A/en
Withdrawn legal-status Critical Current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

  • Treatment Of Steel In Its Molten State (AREA)

Abstract

PROBLEM TO BE SOLVED: To make excellent the ductility, matteability and rollability of an alloy, to facilitate machining therefor and to obtain larger neutron absorging characteristics by using stainless steel as a base material and adding specified weight% of samarium and hafnium thereto. SOLUTION: A neutron absorbing alloy is composed by adding stainless steel with, by weight, 1 to 5% samarium and 0.5 to 4% hafnium. Though this neutron absorbing alloy has neutron absorbing characteristics equivalent to those of boron-contg. stainless steel added with 2% boron, its ductility is not remarkably deteriorated compared to that of general stainless steel such as SUS 304 or the like, so that it is easy to be subjected to machining. Furthermore, there is no problem as for its rollability as well, so that the sheet material is inexpensively produced. A storing rack and a shielding material for a used fuel aggregate or the like are economically and easily produced with increased high shielding properties.

Description

【発明の詳細な説明】DETAILED DESCRIPTION OF THE INVENTION

【0001】[0001]

【発明の属する技術分野】本発明は、主として使用済原
子燃料集合体の保管、貯蔵ラック等の設備に使用して好
適な中性子吸収合金に関するものである。
BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a neutron-absorbing alloy suitable for use mainly in facilities such as storage of spent nuclear fuel assemblies and storage racks.

【0002】[0002]

【従来の技術】使用済燃料の保管施設の設備は、例えば
貯蔵ラックを例にとって説明すると、中性子を吸収させ
るために、従来はステンレス鋼に硼素(B)を1重量%
程度混入して合金化したボロン入りステンレス鋼が用い
られている。しかし、上記ボロン入りステンレス鋼は、
比較的もろく機械加工が困難であり、また溶接も容易で
なく、慎重な取扱いが必要となる。
2. Description of the Related Art In a facility for storing spent fuel, for example, taking a storage rack as an example, in order to absorb neutrons, conventionally, 1% by weight of boron (B) is contained in stainless steel.
A stainless steel containing boron mixed and alloyed to some extent is used. However, the above stainless steel containing boron is
Relatively brittle, difficult to machine, not easy to weld, requires careful handling.

【0003】一方、中性子吸収能力を増加させるために
は、さらに硼素濃度を増加させる必要があるが、この硼
素濃度の増加とともに上記機械的特性が更に悪くなり、
製造上の困難さも増すため、上記硼素濃度は実質的には
前記1重量%程度が限界である。
On the other hand, in order to increase the neutron absorption capacity, it is necessary to further increase the boron concentration. However, with the increase in the boron concentration, the above mechanical properties become worse.
Since the difficulty in production also increases, the above boron concentration is substantially limited to about 1% by weight.

【0004】また、硼素のうち、中性子吸収の大きい同
位体のB10を濃縮した硼素を用いれば、硼素濃度を下げ
ることもできるが、経済的理由から実現してはいない。
[0004] Among the boron, the use of the boron enriched for B 10 large isotopic neutron absorption, it is also possible to reduce the boron concentration, it has not been realized for economic reasons.

【0005】[0005]

【発明が解決しようとする課題】本発明は叙上の如き実
状に対処し、ステンレス鋼に所要量の他の金属を添加
し、新規な中性子吸収合金を見出すことにより、機械加
工も容易で経済的な中性子吸収合金を得ることを目的と
するものである。
SUMMARY OF THE INVENTION The present invention addresses the above-mentioned situation, and is easy and economical to machine by adding the required amount of other metals to stainless steel and finding new neutron absorbing alloys. It is intended to obtain an effective neutron absorption alloy.

【0006】[0006]

【課題を解決するための手段】すなわち、本発明の中性
子吸収合金の特徴は、ステンレス鋼を母材として、合金
全体に対し、1〜5重量%のサマリニウムと0.5〜4
重量%のハフニウムとを夫々添加せしめたことにある。
That is, the feature of the neutron absorbing alloy of the present invention is that, with stainless steel as a base material, 1 to 5% by weight of summarynium and 0.5 to 4% by weight of the entire alloy.
% By weight of hafnium.

【0007】[0007]

【発明の実施の形態】以下さらに添付図面を参照して、
本発明の実施の形態を説明する。
BRIEF DESCRIPTION OF THE DRAWINGS FIG.
An embodiment of the present invention will be described.

【0008】従来のボロン入りステンレス鋼と同等な中
性子吸収特性を得るための上記サマリニウム(Sm)お
よびハフニウム(Hf)の等価混入量は、 ○ サマリニウムは原子個数で硼素(ボロン)の0.1
4倍程度であり、これは重量で上記硼素の2倍程度であ
る。 ○ これに対し、ハフニウムは原子個数で硼素の0.1
倍程度であり、これは重量で上記硼素の1.6倍程度で
ある。
In order to obtain neutron absorption characteristics equivalent to those of the conventional boron-containing stainless steel, the equivalent amounts of the above-mentioned summarynium (Sm) and hafnium (Hf) are as follows:
It is about four times, which is about twice the weight of the above boron. ○ In contrast, hafnium is 0.1% of boron in atomic number.
And about 1.6 times by weight the boron.

【0009】即ち、サマリニウムは熱中性子吸収断面積
が硼素の7倍程度あるので、原子個数では約0.14
倍、また重量では2倍程度で等価となる。しかし、熱外
群の中性子に対してはサマリニウムは吸収が小さい。そ
こで本発明では熱外群の中性子吸収のためハフニウムを
混入する。ハフニウムは中性子エネルギー20eVから
0.8eVの間にいくつもの共鳴吸収帯があるので、熱
外中性子の吸収が非常に大である。
That is, since the thermal neutron absorption cross-sectional area of summarynium is about seven times that of boron, the number of atoms is about 0.14.
It is equivalent to double and about twice in weight. However, for thermal neutrons, the absorption of samarium is small. Therefore, in the present invention, hafnium is mixed for neutron absorption of the epithermal group. Since hafnium has several resonance absorption bands between neutron energies of 20 eV to 0.8 eV, the absorption of epithermal neutrons is very large.

【0010】なお、サマリニウムの代わりにカドミウム
でも同様の効果が得られるが、カドミウムは毒性が強い
ため実用化に難がある。またカドミウムの熱中性子吸収
断面積はサマリニウムの半分以下であるので添加量が多
くなる難点もある。
Although similar effects can be obtained by using cadmium instead of samarium, cadmium is difficult to put into practical use because of its high toxicity. Further, since the thermal neutron absorption cross section of cadmium is less than half of that of samarium, there is a problem that the amount of cadmium added is large.

【0011】[0011]

【実施例】SUS304やSUS316等のステンレス
鋼を母材として、サマリニウムを合金全体の3.8重量
%、ハフニウムを同じく合金全体の3.2重量%それぞ
れ混入して均一組成の合金となした本発明実施例の中性
子吸収合金を製造した。
EXAMPLE Using a stainless steel such as SUS304 or SUS316 as a base material, this alloy was obtained by mixing 3.8% by weight of summarynium and 3.2% by weight of hafnium in the same alloy to form an alloy having a uniform composition. A neutron absorbing alloy according to the invention example was manufactured.

【0012】この本発明の中性子吸収合金は、硼素を2
%混入したボロン入りステンレス鋼と等価の中性子吸収
特性を有しながらも、延性、展性が上記SUS304等
の一般のステンレス鋼に比較して大きく劣ることがない
ため、機械加工が容易である。また、圧延性も問題がな
く、板材等を安価に製造することが可能である。そし
て、この加工性の良さを利用して、使用済原子燃料集合
体の保管、貯蔵用ラック等の設備、または取扱い装置、
プルトニウム燃料検査装置等の構造材および遮蔽材への
応用が可能である。
The neutron absorbing alloy of the present invention contains boron
Although it has a neutron absorption characteristic equivalent to that of boron-containing stainless steel mixed with%, the ductility and malleability are not significantly inferior to those of general stainless steel such as SUS304, so that machining is easy. In addition, there is no problem in rollability, and plate materials and the like can be manufactured at low cost. Utilizing this processability, storage of spent nuclear fuel assemblies, equipment such as storage racks, or handling equipment,
It can be applied to structural materials such as plutonium fuel inspection devices and shielding materials.

【0013】このように、ステンレス鋼に、サマリニウ
ム1〜5重量%およびハフニウム0.5〜4重量%を夫
々混入して合金化することにより、ボロン入りステンレ
ス鋼に換算すると約0.8〜5重量%のボロンを混入し
たボロン入りステンレス鋼に相当する中性子吸収合金が
得られることになる。また、本発明ではサマリニウムを
混入しているため、熱外中性子に対する吸収特性も良好
な合金が得られることになる。なお、上記サマリニウム
およびハフニウムをステンレス鋼に混入する場合、サマ
リニウムは5%、ハフニウムでは4%を夫々越える混入
量となると、均一組成のものを製造するのが次第に困難
となる。しかし、上記数値以下であると、本発明の合金
の製造は容易である。
As described above, by mixing 1-5% by weight of summarynium and 0.5-4% by weight of hafnium into stainless steel and alloying the same, about 0.8-5% in terms of boron-containing stainless steel is obtained. A neutron absorbing alloy corresponding to boron-containing stainless steel mixed with boron by weight of boron is obtained. In addition, in the present invention, since summarynium is mixed, an alloy having good absorption characteristics for epithermal neutrons can be obtained. In addition, when the above-mentioned summarynium and hafnium are mixed into stainless steel, if the content of the summarynium exceeds 5% and the content of the hafnium exceeds 4%, it becomes increasingly difficult to produce a composition having a uniform composition. However, when the value is not more than the above value, the production of the alloy of the present invention is easy.

【0014】[0014]

【発明の効果】以上説明したように、本発明の中性子吸
収合金は、ステンレス鋼に所定量のサマリニウムとハフ
ニウムとを夫々添加したものであり、従来のボロン入り
ステンレス鋼に比較し、延性、展性、圧延性に優れ機械
加工が容易であると共に、より大きな中性子吸収特性を
得ることが可能であり、さらに熱外中性子の吸収にも優
れることから、使用済燃料集合体の保管ラックや遮蔽材
等を経済的にかつ容易に、また遮蔽性を高めて製造しう
るとの顕著な効果を奏するものである。
As described above, the neutron-absorbing alloy of the present invention is obtained by adding a predetermined amount of samarium and hafnium to stainless steel, and is more ductile and more malleable than conventional boron-containing stainless steel. It is easy to machine, has excellent neutron absorption characteristics, and has excellent absorption of epithermal neutrons, so it can be used for storage racks and shielding materials for spent fuel assemblies. It has a remarkable effect that it can be manufactured economically and easily, and can be manufactured with enhanced shielding properties.

Claims (1)

【特許請求の範囲】[Claims] 【請求項1】 ステンレス鋼を母材として、合金全体に
対し、1〜5重量%のサマリニウムと0.5〜4重量%
のハフニウムとを夫々添加せしめたことを特徴とする中
性子吸収合金。
1. A stainless steel as a base material, wherein 1-5% by weight of samarium and 0.5-4% by weight are based on the whole alloy.
A neutron absorbing alloy characterized by the addition of hafnium.
JP9052309A 1997-02-19 1997-02-19 Neutron absorbing alloy Withdrawn JPH10226848A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP9052309A JPH10226848A (en) 1997-02-19 1997-02-19 Neutron absorbing alloy

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP9052309A JPH10226848A (en) 1997-02-19 1997-02-19 Neutron absorbing alloy

Publications (1)

Publication Number Publication Date
JPH10226848A true JPH10226848A (en) 1998-08-25

Family

ID=12911193

Family Applications (1)

Application Number Title Priority Date Filing Date
JP9052309A Withdrawn JPH10226848A (en) 1997-02-19 1997-02-19 Neutron absorbing alloy

Country Status (1)

Country Link
JP (1) JPH10226848A (en)

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A300 Withdrawal of application because of no request for examination

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Effective date: 20040511