JPS54114698A - Preparing carbide fuel pellet for fast neutron reactor - Google Patents

Preparing carbide fuel pellet for fast neutron reactor

Info

Publication number
JPS54114698A
JPS54114698A JP2147778A JP2147778A JPS54114698A JP S54114698 A JPS54114698 A JP S54114698A JP 2147778 A JP2147778 A JP 2147778A JP 2147778 A JP2147778 A JP 2147778A JP S54114698 A JPS54114698 A JP S54114698A
Authority
JP
Japan
Prior art keywords
powder
fuel pellet
processed
zircalloy
fast neutron
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
JP2147778A
Other languages
Japanese (ja)
Inventor
Kazuo Marutani
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.)
Mitsubishi Heavy Industries Ltd
Original Assignee
Mitsubishi Atomic Power Industries Inc
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 Mitsubishi Atomic Power Industries Inc filed Critical Mitsubishi Atomic Power Industries Inc
Priority to JP2147778A priority Critical patent/JPS54114698A/en
Publication of JPS54114698A publication Critical patent/JPS54114698A/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

Abstract

PURPOSE: To prepare a nuclear fuel pellet with a stabilized porous quality and a low density, by means of adding a zircalloy powder to the carbide nuclear fuel.
CONSTITUTION: To UC or (U+Pu)C powder, is added 0.1 to 5 wt% of zircalloy powder, with a hexane injected in the ball mill to provide a uniform mixing. To the mixed powder in a state of paste, are applied a binding agent (polybutenes) and a lubricant with the mixing fully uniformly processed, to effect a drying and beading. The beaded mixed powder is processed a press forming at a pressure of 3 tons/cm2 in a low temperature inactive ambience, being put into the graphite crucible, and processed a vacuum sintering in the graphite resistance type heating furnace. The fuel pellet as obtained in such manner is of low density of 83% T.D.
COPYRIGHT: (C)1979,JPO&Japio
JP2147778A 1978-02-28 1978-02-28 Preparing carbide fuel pellet for fast neutron reactor Pending JPS54114698A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP2147778A JPS54114698A (en) 1978-02-28 1978-02-28 Preparing carbide fuel pellet for fast neutron reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP2147778A JPS54114698A (en) 1978-02-28 1978-02-28 Preparing carbide fuel pellet for fast neutron reactor

Publications (1)

Publication Number Publication Date
JPS54114698A true JPS54114698A (en) 1979-09-06

Family

ID=12056047

Family Applications (1)

Application Number Title Priority Date Filing Date
JP2147778A Pending JPS54114698A (en) 1978-02-28 1978-02-28 Preparing carbide fuel pellet for fast neutron reactor

Country Status (1)

Country Link
JP (1) JPS54114698A (en)

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2016503903A (en) * 2013-01-18 2016-02-08 ウエスチングハウス・エレクトリック・カンパニー・エルエルシー Laser sintering system and method for remotely producing high density pellets containing highly radioactive elements
CN111145924A (en) * 2019-12-31 2020-05-12 西安交通大学 Power density distribution statistical method for porous hexagonal prism type nuclear fuel element
CN111210921A (en) * 2020-01-14 2020-05-29 清华大学 Ageing, washing and drying device for uranium dioxide gel balls

Cited By (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2016503903A (en) * 2013-01-18 2016-02-08 ウエスチングハウス・エレクトリック・カンパニー・エルエルシー Laser sintering system and method for remotely producing high density pellets containing highly radioactive elements
CN111145924A (en) * 2019-12-31 2020-05-12 西安交通大学 Power density distribution statistical method for porous hexagonal prism type nuclear fuel element
CN111145924B (en) * 2019-12-31 2021-08-10 西安交通大学 Power density distribution statistical method for porous hexagonal prism type nuclear fuel element
CN111210921A (en) * 2020-01-14 2020-05-29 清华大学 Ageing, washing and drying device for uranium dioxide gel balls
CN111210921B (en) * 2020-01-14 2022-04-22 清华大学 Ageing, washing and drying device for uranium dioxide gel balls

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