JP3381174B2 - Graphite materials for nuclear reactors - Google Patents

Graphite materials for nuclear reactors

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Publication number
JP3381174B2
JP3381174B2 JP23364091A JP23364091A JP3381174B2 JP 3381174 B2 JP3381174 B2 JP 3381174B2 JP 23364091 A JP23364091 A JP 23364091A JP 23364091 A JP23364091 A JP 23364091A JP 3381174 B2 JP3381174 B2 JP 3381174B2
Authority
JP
Japan
Prior art keywords
graphite
reactor
nuclear reactors
graphite materials
carbon
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.)
Expired - Lifetime
Application number
JP23364091A
Other languages
Japanese (ja)
Other versions
JPH04362064A (en
Inventor
新太郎 石山
Original Assignee
日本原子力研究所
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 日本原子力研究所 filed Critical 日本原子力研究所
Priority to JP23364091A priority Critical patent/JP3381174B2/en
Publication of JPH04362064A publication Critical patent/JPH04362064A/en
Application granted granted Critical
Publication of JP3381174B2 publication Critical patent/JP3381174B2/en
Anticipated expiration legal-status Critical
Expired - Lifetime legal-status Critical Current

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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
    • Y02E30/10—Nuclear fusion reactors
    • 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

Landscapes

  • Ceramic Products (AREA)

Description

【発明の詳細な説明】Detailed Description of the Invention

【０００１】[0001]

【産業上の利用分野】本発明は、原子炉用黒鉛材料に関
する。詳しくは、本発明は、特に高温ガス炉の黒鉛構造
物や核融合炉第１壁の材料として利用できる耐酸化性の
原子炉用黒鉛材料に関する。This invention relates to graphite materials for nuclear reactors. More specifically, the present invention relates to an oxidation-resistant graphite material for a nuclear reactor that can be used as a material for a graphite structure of a high temperature gas reactor or a first wall of a fusion reactor.

【０００２】[0002]

【従来の技術】黒鉛は、硼素（Ｂ）を添加することによ
って、その耐酸化特性が向上することは、従来から知ら
れていた。通常の硼素は、１１Ｂ：１０Ｂがほぼ８対２
の割合で存在している。しかしながら、１０Ｂは、１１
Ｂに比して、熱中性子吸収断面積が２桁程度にも大き
く、中性子減速材として機能し、そのために原子炉の運
転状態が攪乱されるなど、原子炉特性が著しく損なわる
ので、１０Ｂを含む通常の硼素を添加した黒鉛は、使用
することができなかった。また、従来の黒鉛材料は、強
度特性、靭性特性、耐酸特性も良好ではなく、硼素を添
加した黒鉛原料をマトリックス原料とした炭素／炭素コ
ンポジットは、現在まで製造されたことはなかった。2. Description of the Related Art It has been conventionally known that graphite is improved in its oxidation resistance by adding boron (B). Ordinary boron has 11 B: 10 B of about 8 to 2.
Exist in proportion. However, 10 B is 11
Compared to B, the thermal neutron absorption cross section is larger in two orders of magnitude, acts as a neutron moderator, such as the operating state of the reactor because its is disturbed, the reactor characteristics so significantly Sokonawaru, 10 B The usual boron-added graphite containing was not usable. Further, the conventional graphite material is not good in strength property, toughness property, and acid resistance property, and a carbon / carbon composite using a graphite raw material to which boron is added as a matrix raw material has never been produced until now.

【０００３】[0003]

【発明が解決しようとする課題】本発明の目的は、この
ような問題点のない耐酸化性の原子炉用黒鉛材料を提供
することにある。SUMMARY OF THE INVENTION An object of the present invention is to provide an oxidation resistant graphite material for a nuclear reactor which does not have such problems.

【０００４】[0004]

【課題を解決するための手段】本願発明者は、この目的
達成のため鋭意研究の結果、中性子吸収断面積が１０Ｂ
に比べて著しく小さい１１Ｂを添加することによって、
原子炉特性を損なうことなく、黒鉛の耐酸化特性を向上
させ得ることを想到し、本発明の原子炉用黒鉛材料を発
明するに至った。すなわち、本発明の原子炉用黒鉛材料
は、１１Ｂを添加して成ることを特徴とする原子炉用黒
鉛材料である。また、１１Ｂ添加を添加した黒鉛原料を
マトリックス材料として、炭素繊維で強化すると、強度
特性、靭性特性、耐酸特性の向上した炭素／炭素コンポ
ジットが得られる。The inventors of the present invention have made earnest studies to achieve this object, and as a result, have found that the neutron absorption cross section is 10 B
By adding 11 B, which is significantly smaller than
With the idea that the oxidation resistance of graphite can be improved without impairing the reactor characteristics, the inventors have invented the graphite material for a nuclear reactor of the present invention. That is, the graphite material for a nuclear reactor of the present invention is a graphite material for a nuclear reactor, characterized in that 11 B is added. When a graphite raw material added with 11 B is used as a matrix material and reinforced with carbon fibers, a carbon / carbon composite having improved strength characteristics, toughness characteristics, and acid resistance characteristics can be obtained.

【０００５】而して、本発明の原子炉用黒鉛材料は、粉
砕した黒鉛に、１１Ｂの粉末、或いは１１Ｂ４Ｃの粉末
を、１１Ｂとして黒鉛原料全体の最高３０ｗｔ％まで添
加、混煉し、等方加圧成形し、得られた成形体を不活性
雰囲気中で最高３０００℃までの温度で焼結反応させな
がら黒鉛化して製造される。その際使用される１１Ｂの
粉末、或いは１１Ｂ４Ｃの粉末中の１１Ｂは純度１００
％に近いことが望ましい。[0005] In Thus, reactor graphite material of the present invention, the ground graphite powder of 11 B, or a powder of 11 B 4 C, is added up to 30 wt% of the total graphite material as 11 B, mixed It is manufactured by subjecting it to briquetting, isostatic pressing, and graphitizing the resulting molded body while performing a sintering reaction in an inert atmosphere at a temperature of up to 3000 ° C. At that time 11 B of the powder used, or 11 11 B in the powder of B 4 C is pure 100
It is desirable to be close to%.

【０００６】[0006]

【発明の効果】本発明の原子炉用黒鉛材料によって、高
温ガス炉の黒鉛構造物や核融合炉第１壁材料の強度特
性、靭性特性、耐酸特性を向上させることができ、高温
ガス炉、核融合炉を初めとした原子炉の性能向上を図る
ことができる。The graphite material for a nuclear reactor of the present invention can improve the strength characteristics, toughness characteristics and acid resistance characteristics of the graphite structure of the high temperature gas reactor and the first wall material of the fusion reactor. It is possible to improve the performance of nuclear reactors such as fusion reactors.

Claims (2)

(57)【特許請求の範囲】(57) [Claims] 【請求項１】天然硼素（１１Ｂ：１０Ｂ＝８：２）から
１１Ｂを濃縮したものを添加して成ることを特徴とする
原子炉用黒鉛材料。1. From natural boron ( 11 B: 10 B = 8: 2)
11 A graphite material for a nuclear reactor, characterized in that it is obtained by adding a concentrated material of B. 【請求項２】濃縮された１１Ｂを添加した黒鉛をマトリ
ックス材料として炭素繊維で強化して成る炭素／炭素コ
ンポジット。2. A carbon / carbon composite obtained by reinforced carbon fibers using concentrated 11 B-added graphite as a matrix material.
JP23364091A 1991-06-10 1991-06-10 Graphite materials for nuclear reactors Expired - Lifetime JP3381174B2 (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP23364091A JP3381174B2 (en) 1991-06-10 1991-06-10 Graphite materials for nuclear reactors

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP23364091A JP3381174B2 (en) 1991-06-10 1991-06-10 Graphite materials for nuclear reactors

Publications (2)

Publication Number Publication Date
JPH04362064A JPH04362064A (en) 1992-12-15
JP3381174B2 true JP3381174B2 (en) 2003-02-24

Family

ID=16958212

Family Applications (1)

Application Number Title Priority Date Filing Date
JP23364091A Expired - Lifetime JP3381174B2 (en) 1991-06-10 1991-06-10 Graphite materials for nuclear reactors

Country Status (1)

Country Link
JP (1) JP3381174B2 (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN108530078A (en) * 2018-06-01 2018-09-14 大同新成新材料股份有限公司 A kind of forming method of big specification isostatic pressing formed graphite product

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN108530078A (en) * 2018-06-01 2018-09-14 大同新成新材料股份有限公司 A kind of forming method of big specification isostatic pressing formed graphite product
CN108530078B (en) * 2018-06-01 2021-03-05 大同新成新材料股份有限公司 Forming method of large-size isostatic pressing graphite product

Also Published As

Publication number Publication date
JPH04362064A (en) 1992-12-15

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