JPS54141998A - Nuclear fuel component - Google Patents

Nuclear fuel component

Info

Publication number
JPS54141998A
JPS54141998A JP4877978A JP4877978A JPS54141998A JP S54141998 A JPS54141998 A JP S54141998A JP 4877978 A JP4877978 A JP 4877978A JP 4877978 A JP4877978 A JP 4877978A JP S54141998 A JPS54141998 A JP S54141998A
Authority
JP
Japan
Prior art keywords
pellet
nuclear fission
range
fission product
uranium
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
JP4877978A
Other languages
Japanese (ja)
Inventor
Katsumi Une
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.)
Toshiba Corp
Original Assignee
Toshiba Corp
Tokyo Shibaura Electric Co 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 Toshiba Corp, Tokyo Shibaura Electric Co Ltd filed Critical Toshiba Corp
Priority to JP4877978A priority Critical patent/JPS54141998A/en
Publication of JPS54141998A publication Critical patent/JPS54141998A/en
Pending legal-status Critical Current

Links

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
    • Y02E30/30—Nuclear fission reactors

Landscapes

  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

PURPOSE: To reduce the discharge of nuclear fission product and to prevent a crack of the covered tube caused by stress and corrosion by making the uranium-oxygen ratio (O/U) of chemical composition of uranium pellet present in the range from 1.94 to 1.99.
CONSTITUTION: UO2 pellet is a relatively inert substance even at high temperature and has a considerably wide non-stoichiometric range (UO2-X, UO2+X). When the nuclear fission product yielded in the UO2 pellet is discharged out of the pellet in the diffusion process and the chemical composition of pellet is UO2-X, the probability that the product is trapped in the space lattice of oxygen is made greater, and the discharge rate of nuclear fission product from the fuel pellet is made less. Therefore the covered tube made by zirconium alloy can be prevented from a crack caused by stress and corrosion by loading the fuel pellet in which the O/U ratio is selected in the range from 1.94 to 1.99.
COPYRIGHT: (C)1979,JPO&Japio
JP4877978A 1978-04-26 1978-04-26 Nuclear fuel component Pending JPS54141998A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP4877978A JPS54141998A (en) 1978-04-26 1978-04-26 Nuclear fuel component

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP4877978A JPS54141998A (en) 1978-04-26 1978-04-26 Nuclear fuel component

Publications (1)

Publication Number Publication Date
JPS54141998A true JPS54141998A (en) 1979-11-05

Family

ID=12812734

Family Applications (1)

Application Number Title Priority Date Filing Date
JP4877978A Pending JPS54141998A (en) 1978-04-26 1978-04-26 Nuclear fuel component

Country Status (1)

Country Link
JP (1) JPS54141998A (en)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN101894594A (en) * 2009-09-11 2010-11-24 中国原子能科学研究院 Sub-stoichiometric UO2-xPreparation process of annular core block
RU2661492C1 (en) * 2017-05-12 2018-07-17 Акционерное общество "Ведущий научно-исследовательский институт химической технологии" Method of the pelleted ceramic nuclear fuel manufacturing

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN101894594A (en) * 2009-09-11 2010-11-24 中国原子能科学研究院 Sub-stoichiometric UO2-xPreparation process of annular core block
RU2661492C1 (en) * 2017-05-12 2018-07-17 Акционерное общество "Ведущий научно-исследовательский институт химической технологии" Method of the pelleted ceramic nuclear fuel manufacturing

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