JPH0798393A - 原子炉用の部品 - Google Patents

原子炉用の部品

Info

Publication number
JPH0798393A
JPH0798393A JP6097798A JP9779894A JPH0798393A JP H0798393 A JPH0798393 A JP H0798393A JP 6097798 A JP6097798 A JP 6097798A JP 9779894 A JP9779894 A JP 9779894A JP H0798393 A JPH0798393 A JP H0798393A
Authority
JP
Japan
Prior art keywords
stainless steel
component
manganese
stainless
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Withdrawn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
JP6097798A
Other languages
English (en)
Japanese (ja)
Inventor
Alvin J Jacobs
アルヴィン・ジョセフ・ジェイコブス
Gerald M Gordon
ジェラルド・マイロン・ゴードン
Richard A Proebstle
リチャード・アラン・プロエブストル
Mickey O Marlowe
ミッキー・オーヴィル・マーロウィ
Ronald B Adamson
ロナルド・バート・アダムソン
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.)
General Electric Co
Original Assignee
General Electric Co
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 General Electric Co filed Critical General Electric Co
Publication of JPH0798393A publication Critical patent/JPH0798393A/ja
Withdrawn legal-status Critical Current

Links

Classifications

    • C—CHEMISTRY; METALLURGY
    • C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
    • C22C—ALLOYS
    • C22C38/00—Ferrous alloys, e.g. steel alloys
    • C22C38/18—Ferrous alloys, e.g. steel alloys containing chromium
    • C22C38/40—Ferrous alloys, e.g. steel alloys containing chromium with nickel
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/02—Fuel elements
    • G21C3/04—Constructional details
    • G21C3/06—Casings; Jackets
    • G21C3/07—Casings; Jackets characterised by their material, e.g. alloys
    • 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
    • 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
    • Y10—TECHNICAL SUBJECTS COVERED BY FORMER USPC
    • Y10S—TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y10S376/00—Induced nuclear reactions: processes, systems, and elements
    • Y10S376/90—Particular material or material shapes for fission reactors

Landscapes

  • Engineering & Computer Science (AREA)
  • Chemical & Material Sciences (AREA)
  • Metallurgy (AREA)
  • Physics & Mathematics (AREA)
  • Plasma & Fusion (AREA)
  • High Energy & Nuclear Physics (AREA)
  • General Engineering & Computer Science (AREA)
  • Materials Engineering (AREA)
  • Mechanical Engineering (AREA)
  • Organic Chemistry (AREA)
  • Preventing Corrosion Or Incrustation Of Metals (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)
  • Powder Metallurgy (AREA)
JP6097798A 1993-05-13 1994-05-12 原子炉用の部品 Withdrawn JPH0798393A (ja)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
US6062893A 1993-05-13 1993-05-13
US060628 1993-05-13

Publications (1)

Publication Number Publication Date
JPH0798393A true JPH0798393A (ja) 1995-04-11

Family

ID=22030739

Family Applications (1)

Application Number Title Priority Date Filing Date
JP6097798A Withdrawn JPH0798393A (ja) 1993-05-13 1994-05-12 原子炉用の部品

Country Status (4)

Country Link
US (1) US5539794A (enExample)
EP (1) EP0624659A1 (enExample)
JP (1) JPH0798393A (enExample)
TW (1) TW250567B (enExample)

Families Citing this family (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US6128361A (en) * 1996-03-26 2000-10-03 General Electric Company Coating for reducing corrosion of zirconium-based alloys induced by . .beta-particle irradiation
SE512804C2 (sv) * 1998-09-11 2000-05-15 Abb Ab Anordning och förfarande för att förhindra skuggkorrosion
US6259758B1 (en) 1999-02-26 2001-07-10 General Electric Company Catalytic hydrogen peroxide decomposer in water-cooled reactors
US20100014624A1 (en) * 2008-07-17 2010-01-21 Global Nuclear Fuel - Americas, Llc Nuclear reactor components including material layers to reduce enhanced corrosion on zirconium alloys used in fuel assemblies and methods thereof

Family Cites Families (12)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
GB1210064A (en) * 1960-02-02 1970-10-28 Atomic Energy Authority Uk Improvements in or relating to austenitic stainless steels
US3159479A (en) * 1962-11-28 1964-12-01 Int Nickel Co Austenitic chromium-nickel stainless steels resistant to stress-corrosion cracking
US4231795A (en) * 1978-06-22 1980-11-04 The United States Of America As Represented By The United States Department Of Energy High weldability nickel-base superalloy
DE3248686A1 (de) * 1982-12-30 1984-07-12 Kraftwerk Union AG, 4330 Mülheim Verfahren zum herstellen eines huellrohres aus einer zirkoniumlegierung fuer kernreaktorbrennstoff eines kernreaktorbrennelementes
JPS59143049A (ja) * 1983-02-02 1984-08-16 Daido Steel Co Ltd 低透磁率オ−ステナイト系ステンレス鋼
JPS59153858A (ja) * 1983-02-23 1984-09-01 Nippon Kokan Kk <Nkk> 靭性および耐食性の優れたクロム・ニツケル・鉄合金
US5196163A (en) * 1986-07-29 1993-03-23 Mitsubishi Materials Corporation Highly corrosion-resistant zirconium alloy for use as nuclear reactor fuel cladding material
US4798633A (en) * 1986-09-25 1989-01-17 Inco Alloys International, Inc. Nickel-base alloy heat treatment
US4836976A (en) * 1987-04-20 1989-06-06 General Electric Company Light water reactor cores with increased resistance to stress corrosion cracking
US5120614A (en) * 1988-10-21 1992-06-09 Inco Alloys International, Inc. Corrosion resistant nickel-base alloy
JPH0387334A (ja) * 1989-08-29 1991-04-12 Kobe Steel Ltd 極低温用非磁性構造材料
JP2574917B2 (ja) * 1990-03-14 1997-01-22 株式会社日立製作所 耐応力腐食割れ性に優れたオーステナイト鋼及びその用途

Also Published As

Publication number Publication date
US5539794A (en) 1996-07-23
EP0624659A1 (en) 1994-11-17
TW250567B (enExample) 1995-07-01

Similar Documents

Publication Publication Date Title
EP0345531B1 (en) Ductile irradiated zirconium alloy
KR0180770B1 (ko) 조사후 특성이 개선된 지르코늄 합금
US5211774A (en) Zirconium alloy with superior ductility
Diercks et al. Alloying and impurity effects in vanadium-base alloys
KR100261666B1 (ko) 저 부식성과 고강도를 갖는 지르코늄합금 조성물
EP0532830A2 (en) Zirconium alloy with superior ductility
US5278882A (en) Zirconium alloy with superior corrosion resistance
US8958523B2 (en) Spacer grid
Jenssen et al. Importance of molybdenum on irradiation-assisted stress corrosion cracking in austenitic stainless steels
Manahan et al. A phenomenological investigation of in-reactor cracking of type 304 stainless steel control rod cladding
JP2014080664A (ja) 高耐食性オーステナイト系ステンレス鋼
JPS63303038A (ja) 応力腐食割れに対する抵抗性の増大した軽水炉の炉心
Chopra et al. Crack growth rates and fracture toughness of irradiated austenitic stainless steels in BWR environments.
JPH0798393A (ja) 原子炉用の部品
LeSurf¹ Zirconium Alloy
US3440037A (en) Stainless steel alloy exhibiting resistance to embrittlement by neutron irradiation
JP2926519B2 (ja) タングステン及びニッケルを含有するジルコニウム合金
JP2535114B2 (ja) 原子力プラント用部材の製造方法
JP3009147B2 (ja) 中性子照射下で高温高圧水にさらされるオーステナイト鋼及びその用途
RU2325459C2 (ru) Малоактивируемая коррозионно-стойкая и радиационно стойкая хромистая сталь
Chen et al. Irradiation-assisted stress corrosion cracking of austenitic stainless steels in BWR environments
JPH05171359A (ja) 窒素とホウ素の含有量を極めて低くしたオーステナイト系ステンレス鋼
Hamilton et al. Tensile properties of neutron irradiated A212B pressure vessel steel
Grossbeck et al. Swelling and tensile properties of EBR-II-irradiated tantalum alloys for space reactor applications
JPH0649915B2 (ja) 原子炉炉心機器用ステンレス鋼とその製造方法

Legal Events

Date Code Title Description
A300 Application deemed to be withdrawn because no request for examination was validly filed

Free format text: JAPANESE INTERMEDIATE CODE: A300

Effective date: 20010731