JPS6051076B2 - 核燃料物質の回収方法 - Google Patents

核燃料物質の回収方法

Info

Publication number
JPS6051076B2
JPS6051076B2 JP53053695A JP5369578A JPS6051076B2 JP S6051076 B2 JPS6051076 B2 JP S6051076B2 JP 53053695 A JP53053695 A JP 53053695A JP 5369578 A JP5369578 A JP 5369578A JP S6051076 B2 JPS6051076 B2 JP S6051076B2
Authority
JP
Japan
Prior art keywords
nuclear fuel
sheath
fuel material
zinc
metal
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
Application number
JP53053695A
Other languages
English (en)
Japanese (ja)
Other versions
JPS53139097A (en
Inventor
ウイリアム・ベイテイ
アルフレツド・レオナ−ド・ミルズ
ジヨン・ア−ノルド・ウイリアムズ
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.)
UK Atomic Energy Authority
Original Assignee
UK Atomic Energy Authority
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 UK Atomic Energy Authority filed Critical UK Atomic Energy Authority
Publication of JPS53139097A publication Critical patent/JPS53139097A/ja
Publication of JPS6051076B2 publication Critical patent/JPS6051076B2/ja
Expired legal-status Critical Current

Links

Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
    • G21C19/34—Apparatus or processes for dismantling nuclear fuel, e.g. before reprocessing ; Apparatus or processes for dismantling strings of spent fuel elements
    • C—CHEMISTRY; METALLURGY
    • C21—METALLURGY OF IRON
    • C21D—MODIFYING THE PHYSICAL STRUCTURE OF FERROUS METALS; GENERAL DEVICES FOR HEAT TREATMENT OF FERROUS OR NON-FERROUS METALS OR ALLOYS; MAKING METAL MALLEABLE, e.g. BY DECARBURISATION OR TEMPERING
    • C21D1/00—General methods or devices for heat treatment, e.g. annealing, hardening, quenching or tempering
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
    • G21C19/34—Apparatus or processes for dismantling nuclear fuel, e.g. before reprocessing ; Apparatus or processes for dismantling strings of spent fuel elements
    • G21C19/38—Chemical means only
    • 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
    • Y10T—TECHNICAL SUBJECTS COVERED BY FORMER US CLASSIFICATION
    • Y10T225/00—Severing by tearing or breaking
    • Y10T225/10—Methods
    • Y10T225/12—With preliminary weakening

Landscapes

  • Engineering & Computer Science (AREA)
  • Physics & Mathematics (AREA)
  • Chemical & Material Sciences (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Plasma & Fusion (AREA)
  • Thermal Sciences (AREA)
  • General Chemical & Material Sciences (AREA)
  • Chemical Kinetics & Catalysis (AREA)
  • Crystallography & Structural Chemistry (AREA)
  • Mechanical Engineering (AREA)
  • Materials Engineering (AREA)
  • Metallurgy (AREA)
  • Organic Chemistry (AREA)
  • Manufacture And Refinement Of Metals (AREA)
  • Solid-Phase Diffusion Into Metallic Material Surfaces (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)
JP53053695A 1977-05-11 1978-05-04 核燃料物質の回収方法 Expired JPS6051076B2 (ja)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
GB19861 1977-05-11
GB1986177 1977-05-11

Publications (2)

Publication Number Publication Date
JPS53139097A JPS53139097A (en) 1978-12-05
JPS6051076B2 true JPS6051076B2 (ja) 1985-11-12

Family

ID=10136425

Family Applications (1)

Application Number Title Priority Date Filing Date
JP53053695A Expired JPS6051076B2 (ja) 1977-05-11 1978-05-04 核燃料物質の回収方法

Country Status (5)

Country Link
US (1) US4248836A (OSRAM)
JP (1) JPS6051076B2 (OSRAM)
DE (1) DE2820060A1 (OSRAM)
FR (1) FR2390808B1 (OSRAM)
GB (1) GB2000358B (OSRAM)

Families Citing this family (7)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE3011760A1 (de) * 1980-03-26 1981-10-01 Kraftwerk Union AG, 4330 Mülheim Verfahren zum zerlegen abgebrannter kernreaktorbrennstaebe
FR2485396A1 (fr) * 1980-06-25 1981-12-31 Commissariat Energie Atomique Procede et dispositif pour la denaturation par concassage de pieces metalliques
DE3103900C2 (de) * 1981-02-05 1984-02-02 Kernforschungsanlage Jülich GmbH, 5170 Jülich Anlage zum Aufbereiten graphitischer Brennelemente von Hochtemperatur-Kernreaktoren
JPS61194395A (ja) * 1985-02-25 1986-08-28 日本核燃料開発株式会社 使用済核燃料要素の破壊方法
FR2698715B1 (fr) * 1992-11-27 1995-02-17 Framatome Sa Procédé et dispositif de traitement d'éléments activés par irradiation en vue de leur élimination.
JP2005043331A (ja) 2003-07-09 2005-02-17 Japan Nuclear Cycle Development Inst States Of Projects 使用済核燃料の脱被覆方法及び脱被覆装置
CN109722522A (zh) * 2019-03-06 2019-05-07 中国大唐集团科学技术研究院有限公司华中电力试验研究院 一种脆化hr3c钢管的恢复性热处理工艺

Family Cites Families (15)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
GB865742A (en) * 1958-05-29 1961-04-19 Du Pont Improvements in the treatment of refractory metals
GB922955A (en) * 1959-07-14 1963-04-03 Hokuriku Kako Kabushiki Kaisha Prcoess for the manufacture of pulverized iron
US3089751A (en) * 1960-11-25 1963-05-14 Richard J Beaver Selective separation of uranium from ferritic stainless steels
GB900216A (en) * 1961-04-14 1962-07-04 Titanium Metals Corp Method of reclaiming scrap metal consisting of titanium or titanium-base alloys
US4045356A (en) * 1963-06-24 1977-08-30 The Boeing Company Fracturing agent
DE1464978A1 (de) * 1964-11-13 1969-06-26 Kaba Dipl Ing E L Verfahren zum Wiederaufarbeiten gebrauchten Spaltstoffes von Atomreaktoren
BE705939A (OSRAM) * 1967-10-31 1968-04-30
BE717446A (OSRAM) * 1968-07-01 1968-12-16
US3567648A (en) * 1969-04-08 1971-03-02 Atomic Energy Commission Dissolution of stainless steel clad nuclear fuel elements
BE746819A (nl) * 1970-03-04 1970-08-17 Studiecentrum Kernenergi Werkwijze om een bundel splijtstofelementen voor de opwerking te ontdoen van hun omhulsel (uitv. w. goossens, g. dumont en r. harnie),
US3763770A (en) * 1970-12-15 1973-10-09 Allied Chem Method for shearing spent nuclear fuel bundles
GB1381726A (en) * 1971-07-29 1975-01-29 British Steel Corp Scrap treatment
US3791881A (en) * 1972-03-02 1974-02-12 Us Navy Annealing treatment for controlling warhead fragmentation size distribution
US3867510A (en) * 1973-04-23 1975-02-18 Atomic Energy Commission Process for recovering uranium and plutonium from irradiated nuclear fuel oxides
US4128694A (en) * 1977-05-09 1978-12-05 Monsanto Company Laminates comprising a plasticized interlayer

Also Published As

Publication number Publication date
GB2000358A (en) 1979-01-04
FR2390808A1 (fr) 1978-12-08
DE2820060C2 (OSRAM) 1988-07-28
US4248836A (en) 1981-02-03
JPS53139097A (en) 1978-12-05
FR2390808B1 (fr) 1985-11-15
DE2820060A1 (de) 1978-12-07
GB2000358B (en) 1982-01-27

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