FR2266939A2 - Nuclear fuel element plates eg zircalloy cladded - divided internally into separately wrapped small pieces - Google Patents

Nuclear fuel element plates eg zircalloy cladded - divided internally into separately wrapped small pieces

Info

Publication number
FR2266939A2
FR2266939A2 FR7411821A FR7411821A FR2266939A2 FR 2266939 A2 FR2266939 A2 FR 2266939A2 FR 7411821 A FR7411821 A FR 7411821A FR 7411821 A FR7411821 A FR 7411821A FR 2266939 A2 FR2266939 A2 FR 2266939A2
Authority
FR
France
Prior art keywords
fuel
zircalloy
fuel element
cladded
cladding
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.)
Granted
Application number
FR7411821A
Other languages
French (fr)
Other versions
FR2266939B2 (en
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.)
Commissariat a lEnergie Atomique et aux Energies Alternatives CEA
Original Assignee
Commissariat a lEnergie Atomique CEA
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 Commissariat a lEnergie Atomique CEA filed Critical Commissariat a lEnergie Atomique CEA
Priority to FR7411821A priority Critical patent/FR2266939A2/en
Priority to SE7408480D priority patent/SE7408480L/xx
Priority to GB2856674A priority patent/GB1445269A/en
Priority to CH890474A priority patent/CH590541A5/xx
Priority to NL7408987A priority patent/NL7408987A/en
Priority to IT69150/74A priority patent/IT1014475B/en
Priority to DE2432407A priority patent/DE2432407A1/en
Priority to JP49077242A priority patent/JPS5744958B2/ja
Priority to ES428051A priority patent/ES428051A1/en
Publication of FR2266939A2 publication Critical patent/FR2266939A2/en
Priority to US05/727,730 priority patent/US4038135A/en
Application granted granted Critical
Publication of FR2266939B2 publication Critical patent/FR2266939B2/fr
Granted legal-status Critical Current

Links

Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C3/00Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/30Assemblies of a number of fuel elements in the form of a rigid unit
    • G21C3/36Assemblies of plate-shaped fuel elements or coaxial tubes
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C21/00Apparatus or processes specially adapted to the manufacture of reactors or parts thereof
    • G21C21/02Manufacture of fuel elements or breeder elements contained in non-active casings
    • 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

  • Engineering & Computer Science (AREA)
  • Physics & Mathematics (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Manufacturing & Machinery (AREA)
  • Laminated Bodies (AREA)

Abstract

The minimise the escape of radio-active fission prods. in the event of a fuel element wall leak, plate type elements are made up of many uniform shaped pieces of fuel matl. each wrapped separately. Various methods of wrapping are proposed. The assembled pieces making up the fuel element are wrapped overall and a good heat-transfer bond achieved between fuel and cladding by high temp. fusion welding. E.g. with zirconium alloy cladding and ceramic fuel matl. the assembled element is heated for 4 hours at 830 degrees and 2,000 atm pressure in Helium. The internal wrapping is e.g. 0.4 mm and the main cladding 4 mm zircalloy.
FR7411821A 1973-07-06 1974-04-03 Nuclear fuel element plates eg zircalloy cladded - divided internally into separately wrapped small pieces Granted FR2266939A2 (en)

Priority Applications (10)

Application Number Priority Date Filing Date Title
FR7411821A FR2266939A2 (en) 1974-04-03 1974-04-03 Nuclear fuel element plates eg zircalloy cladded - divided internally into separately wrapped small pieces
SE7408480D SE7408480L (en) 1973-07-06 1974-06-27
GB2856674A GB1445269A (en) 1973-07-06 1974-06-27 Emthod of fabrication of a ceramic nuclear fuel element
CH890474A CH590541A5 (en) 1973-07-06 1974-06-28
NL7408987A NL7408987A (en) 1973-07-06 1974-07-03 PLATE-SHAPED NUCLEAR FLEXIBLE ELEMENT AND METHOD FOR MANUFACTURING IT.
IT69150/74A IT1014475B (en) 1973-07-06 1974-07-05 NUCLEAR FUEL ELEMENT AND PROCEDURE FOR ITS FACTORY
DE2432407A DE2432407A1 (en) 1973-07-06 1974-07-05 PLATE-SHAPED NUCLEAR FUEL ELEMENT AND METHOD OF MANUFACTURING THE SAME
JP49077242A JPS5744958B2 (en) 1973-07-06 1974-07-05
ES428051A ES428051A1 (en) 1973-07-06 1974-07-06 Emthod of fabrication of a ceramic nuclear fuel element
US05/727,730 US4038135A (en) 1973-07-06 1976-09-29 Plate type nuclear fuel element and a method of fabrication of said element

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
FR7411821A FR2266939A2 (en) 1974-04-03 1974-04-03 Nuclear fuel element plates eg zircalloy cladded - divided internally into separately wrapped small pieces

Publications (2)

Publication Number Publication Date
FR2266939A2 true FR2266939A2 (en) 1975-10-31
FR2266939B2 FR2266939B2 (en) 1978-11-03

Family

ID=9137233

Family Applications (1)

Application Number Title Priority Date Filing Date
FR7411821A Granted FR2266939A2 (en) 1973-07-06 1974-04-03 Nuclear fuel element plates eg zircalloy cladded - divided internally into separately wrapped small pieces

Country Status (1)

Country Link
FR (1) FR2266939A2 (en)

Also Published As

Publication number Publication date
FR2266939B2 (en) 1978-11-03

Similar Documents

Publication Publication Date Title
GB2056055B (en) Measuring the linear heat generation rate of a nuclear reactor fuel pin
ES440477A1 (en) Nuclear fuel elements having a composite cladding
JPS5547485A (en) Method of making inertia confinement nuclear fusion fuel target and fuel target made thereby
GB897145A (en) Improvements in or relating to fuel elements for nuclear reactors
SE7611717L (en) PRESSURE HOLD TANK FOR PRESSURE WATER REACTORS
ES446545A1 (en) Getter for nuclear fuel elements
GB790389A (en) Improvements in or relating to fuel elements for use in nuclear reactors
FR2236250A1 (en) Nuclear fuel element plates eg zircalloy cladded - divided internally into separately wrapped small pieces
FR2266939A2 (en) Nuclear fuel element plates eg zircalloy cladded - divided internally into separately wrapped small pieces
GB2004074B (en) Method for verifying the pressure in a nuclear reactor fuel rod
ES472678A1 (en) Method for protecting the casing tubes of nuclear reactor fuel rods
JPS5619494A (en) Method of positioning leaked fuel rod in nuclear fuel assembly
JPS57182197A (en) Device for protecting leakage of fissionable gas in nuclear fuel rod
GB829139A (en) Improvements in or relating to nuclear reactor fuel elements
Notley Calculation of Fission-Product Gas Pressures in Operating UO2 Fuel Elements
GB989393A (en) Improvements in or relating to nuclear reactor fuel elements
NO161765C (en) INSTRUMENTED MEASURING HEAD FOR MEASURING GAS PRESSURE IN NUCLEAR FUEL RODS.
GB1493090A (en) Tritium removal and retention device
JPS5438485A (en) Pud for transport of fuel assembly
Keegstra et al. Finite Element Stress Analysis of Interacting Fuel Pellet and Canning under Fast Reactor Condition
GB1445269A (en) Emthod of fabrication of a ceramic nuclear fuel element
IT1137284B (en) PROCEDURE FOR MANUFACTURING ZIRCONIUM ALLOY PIPES INTENDED FOR USE IN REACTORS AND NUCLEAR ENERGY
CA1029464A (en) Ultrasonic inspection recess in heat exchanger and nuclear steam generator tubesheets
BENSKY et al. Spent fuel storage and isolation(Conferences)
KAEMPF et al. Treatment of the mechanical and thermal relations of fuel rods in Saturn 1(Calculating time history of fuel pin concerning radial distribution of temperature, stress, porosity and geometry changes in Saturn 1)