JPS5499897A - Nuclear fuel rod - Google Patents

Nuclear fuel rod

Info

Publication number
JPS5499897A
JPS5499897A JP635678A JP635678A JPS5499897A JP S5499897 A JPS5499897 A JP S5499897A JP 635678 A JP635678 A JP 635678A JP 635678 A JP635678 A JP 635678A JP S5499897 A JPS5499897 A JP S5499897A
Authority
JP
Japan
Prior art keywords
cladding tube
gas
lining layer
irradiation
nuclear fuel
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
JP635678A
Other languages
Japanese (ja)
Inventor
Yasuo Tanabe
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 JP635678A priority Critical patent/JPS5499897A/en
Publication of JPS5499897A publication Critical patent/JPS5499897A/en
Pending legal-status Critical Current

Links

Classifications

    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

Landscapes

  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

PURPOSE: To prevent the stress corrosion cracking of a cladding tube, by means of setting up a lining layer at the inner surface of the cladding tube.
CONSTITUTION: A lining layer 8 is coated containing Beryllium at the inner surface of a cladding tube 30, and therein a fuel pellet 4 is contained. The Beryllium contained in the lining layer 8 releases α particles, namely He atomic nucleus by means of receiving the irradiation of fast neutron generating during the reactor is in operation. Accordingly, He gas is accumulated attended with the irradiation of the nuclear fuel rod in gaps 7 of the cladding tube 30 and within a plenum, and the mol fraction of the He gas is increased. This He gas is a good gas in heat conductivity and the deteriozation of a gap conductance is restrained, and the temp. lowering of the fuel pellet is brought. And the discharging rate of F.P. gases are lowered, and the generation of corrosive atomosphere can be prevented.
COPYRIGHT: (C)1979,JPO&Japio
JP635678A 1978-01-24 1978-01-24 Nuclear fuel rod Pending JPS5499897A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP635678A JPS5499897A (en) 1978-01-24 1978-01-24 Nuclear fuel rod

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP635678A JPS5499897A (en) 1978-01-24 1978-01-24 Nuclear fuel rod

Publications (1)

Publication Number Publication Date
JPS5499897A true JPS5499897A (en) 1979-08-07

Family

ID=11636078

Family Applications (1)

Application Number Title Priority Date Filing Date
JP635678A Pending JPS5499897A (en) 1978-01-24 1978-01-24 Nuclear fuel rod

Country Status (1)

Country Link
JP (1) JPS5499897A (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
WO1994025964A1 (en) * 1993-05-04 1994-11-10 Siemens Aktiengesellschaft Fuel rod with predetermined anticipated perforation

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
WO1994025964A1 (en) * 1993-05-04 1994-11-10 Siemens Aktiengesellschaft Fuel rod with predetermined anticipated perforation
US5790622A (en) * 1993-05-04 1998-08-04 Siemens Aktiengesellschaft Fuel rod having predetermined secondary damage

Similar Documents

Publication Publication Date Title
US2879216A (en) Neutronic reactor
US3925151A (en) Nuclear fuel element
Vitanza et al. Fission gas release from UO 2 pellet fuel at high burn-up
Reynolds et al. Irradiation behavior of experimental fuel particles containing chemically vapor deposited zirconium carbide coatings
US4271207A (en) Process for the coating of particles for the production of fuel and/or absorbing elements for nuclear reactors and apparatus therefor
US3992258A (en) Coated nuclear fuel particles and process for making the same
US3325363A (en) Carbon coated nuclear fuel and poison particles
US3165422A (en) Ceramic coated fuel particles
EP0145336B1 (en) Method for minimizing the permeation release of tritrium through a nuclear reactor component
US4167444A (en) Removal of impurities from the coolant gas of gas-cooled high temperature nuclear reactors
US2809931A (en) Neutronic reactor system
US3249509A (en) Nuclear fuel particles coated with mixture of pyrolytic carbon and silicon carbide
US2830944A (en) Neutronic reactor
JPS5499897A (en) Nuclear fuel rod
US3312597A (en) Coated particle fuels for nuclear reactors
US3224944A (en) Ceramic-matrix-type fuel element with graphite fabric affixed to exterior surface
Oxley et al. Kinetics of carbon deposition in a fluidized bed
US2938784A (en) Nuclear fuel composition
US3764469A (en) Carbon silicon coating alloys for improved irradiation stability
US3861998A (en) Method of operating a neutronic reactor
US2850447A (en) Neutronic reactor
Fillmore Two-Group Calculation of the Critical Core Size of the SRE Reactor
US3115446A (en) Fuel elements for nuclear reactors
US2976227A (en) Neutronic reactor
US2990357A (en) Method and apparatus for controlling neutron density