FR2192319A1 - Heavy isotope fissile fuel mixture - with breeder material content for use in neutron flux monitors - Google Patents

Heavy isotope fissile fuel mixture - with breeder material content for use in neutron flux monitors

Info

Publication number
FR2192319A1
FR2192319A1 FR7224986A FR7224986A FR2192319A1 FR 2192319 A1 FR2192319 A1 FR 2192319A1 FR 7224986 A FR7224986 A FR 7224986A FR 7224986 A FR7224986 A FR 7224986A FR 2192319 A1 FR2192319 A1 FR 2192319A1
Authority
FR
France
Prior art keywords
neutron flux
fuel mixture
material content
heavy isotope
fissile 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.)
Granted
Application number
FR7224986A
Other languages
French (fr)
Other versions
FR2192319B1 (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 FR7224986A priority Critical patent/FR2192319A1/en
Publication of FR2192319A1 publication Critical patent/FR2192319A1/en
Application granted granted Critical
Publication of FR2192319B1 publication Critical patent/FR2192319B1/fr
Granted legal-status Critical Current

Links

Classifications

    • H—ELECTRICITY
    • H01—ELECTRIC ELEMENTS
    • H01J—ELECTRIC DISCHARGE TUBES OR DISCHARGE LAMPS
    • H01J47/00—Tubes for determining the presence, intensity, density or energy of radiation or particles
    • H01J47/12—Neutron detector tubes, e.g. BF3 tubes

Landscapes

  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

The mixture consists of >=1 heavy fissile isotope and >=1 heavy isotope which becomes fissile with exposure to neutron flux. The mixture is such that the fission cross section is approx. constant with time under a given neutron flux spectrum. The mixture contains 15-30% of U-235. It is either of U-234 and U-235 or of U-235 and U-238 of which 16% is U-235. Stable sensitivity is obtd. together with a long life.
FR7224986A 1972-07-10 1972-07-10 Heavy isotope fissile fuel mixture - with breeder material content for use in neutron flux monitors Granted FR2192319A1 (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
FR7224986A FR2192319A1 (en) 1972-07-10 1972-07-10 Heavy isotope fissile fuel mixture - with breeder material content for use in neutron flux monitors

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
FR7224986A FR2192319A1 (en) 1972-07-10 1972-07-10 Heavy isotope fissile fuel mixture - with breeder material content for use in neutron flux monitors

Publications (2)

Publication Number Publication Date
FR2192319A1 true FR2192319A1 (en) 1974-02-08
FR2192319B1 FR2192319B1 (en) 1974-12-27

Family

ID=9101631

Family Applications (1)

Application Number Title Priority Date Filing Date
FR7224986A Granted FR2192319A1 (en) 1972-07-10 1972-07-10 Heavy isotope fissile fuel mixture - with breeder material content for use in neutron flux monitors

Country Status (1)

Country Link
FR (1) FR2192319A1 (en)

Non-Patent Citations (2)

* Cited by examiner, † Cited by third party
Title
DECEMBRE 1969, PAGES 375-380, ARTICLE DE H.WEISS, "A CORRELATION METHOD FOR NEUTRON FLU MEASUREMENT IN NUCLEAR REACTORS.) *
REVUE ALLEMANDE "ATOMKERNENERGIE" ATKE , VOLUME 14, NO. 6, NOVEMBRE *

Also Published As

Publication number Publication date
FR2192319B1 (en) 1974-12-27

Similar Documents

Publication Publication Date Title
ES8103444A1 (en) Determining fissile content of nuclear fuel elements
SE7710681L (en) NUCLEAR FUEL CARTRIDGE
BE785939A (en) IMPROVEMENTS IN THE FUEL ELEMENTS OF NUCLEAR REACTORS
BE755643A (en) IMPROVEMENTS IN THE FUEL ELEMENTS OF NUCLEAR REACTORS
GB1062247A (en) Long lifetime nuclear reactor
GB1186652A (en) A Fuel and Breeding Element for Nuclear Reactors
FR2192319A1 (en) Heavy isotope fissile fuel mixture - with breeder material content for use in neutron flux monitors
GB1299038A (en) Fast reactor
BE785941A (en) IMPROVEMENTS IN THE FUEL ELEMENTS OF NUCLEAR REACTORS
JPS52104693A (en) Neutron detector for monitoring in reactor
GB957624A (en) Improvements in or relating to nuclear reactor fuel elements
ES460081A1 (en) Nuclear fuel assembly and process
JPS5357388A (en) Nuclear reactor
FR76850E (en) Improvements to processes for producing nuclear reactor components
GB1164980A (en) Process for Depleting <283>PuO2 in <17>O and <18>O.
GB1404520A (en)
GB1046965A (en) Improvements in or relating to nuclear fuels
KR830003923A (en) Mixed Oxide Nuclear Fuel Pellet
FR2202342A1 (en) Neutron collimator and filter - collimator covered internally with neutron absorber and having gamma screens
GB861602A (en) Improvements in or relating to nuclear reactor fuel compositions
FR2009838A2 (en) Fuel cartridges for nuclear reactors
BE590543A (en) Improvement in handling systems for fissile material elements of a nuclear reactor.
JPS52104683A (en) Nuclear reactor
JPS53115494A (en) Fuel particle distribution measurement of nuclear fuel compact
BELL et al. Long-term hazard of radioactive wastes produced by the Enriched uranium, Pu-U-238, and U-233-Th fuel cycles(Long term hazard of high level and alpha radioactive wastes produced by enriched uranium, Pu-(U-238), and(U-233)-Th fuel cycles)