GB1235324A - A method of and apparatus for determining the content of fissile material in fuel samples or fuel elements of nuclear reactors - Google Patents

A method of and apparatus for determining the content of fissile material in fuel samples or fuel elements of nuclear reactors

Info

Publication number
GB1235324A
GB1235324A GB27761/68A GB2776168A GB1235324A GB 1235324 A GB1235324 A GB 1235324A GB 27761/68 A GB27761/68 A GB 27761/68A GB 2776168 A GB2776168 A GB 2776168A GB 1235324 A GB1235324 A GB 1235324A
Authority
GB
United Kingdom
Prior art keywords
activity
reactor
fuel
fissile material
arrangement
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.)
Expired
Application number
GB27761/68A
Other languages
English (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.)
Forschungszentrum Juelich GmbH
Original Assignee
Kernforschungsanlage Juelich GmbH
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 Kernforschungsanlage Juelich GmbH filed Critical Kernforschungsanlage Juelich GmbH
Publication of GB1235324A publication Critical patent/GB1235324A/en
Expired legal-status Critical Current

Links

Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C17/00—Monitoring; Testing ; Maintaining
    • G21C17/06—Devices or arrangements for monitoring or testing fuel or fuel elements outside the reactor core, e.g. for burn-up, for contamination
    • G21C17/063—Burn-up control
    • 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

  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)
GB27761/68A 1967-06-22 1968-06-11 A method of and apparatus for determining the content of fissile material in fuel samples or fuel elements of nuclear reactors Expired GB1235324A (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
DEK0062612 1967-06-22

Publications (1)

Publication Number Publication Date
GB1235324A true GB1235324A (en) 1971-06-09

Family

ID=7230699

Family Applications (1)

Application Number Title Priority Date Filing Date
GB27761/68A Expired GB1235324A (en) 1967-06-22 1968-06-11 A method of and apparatus for determining the content of fissile material in fuel samples or fuel elements of nuclear reactors

Country Status (4)

Country Link
BE (1) BE716988A (GUID-C5D7CC26-194C-43D0-91A1-9AE8C70A9BFF.html)
FR (1) FR1570956A (GUID-C5D7CC26-194C-43D0-91A1-9AE8C70A9BFF.html)
GB (1) GB1235324A (GUID-C5D7CC26-194C-43D0-91A1-9AE8C70A9BFF.html)
NL (1) NL6808660A (GUID-C5D7CC26-194C-43D0-91A1-9AE8C70A9BFF.html)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
RU2185667C1 (ru) * 2001-02-06 2002-07-20 Федеральное государственное унитарное предприятие "Сибирский химический комбинат" Способ и система контроля обогащения гексафторида урана

Families Citing this family (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE1938836A1 (de) * 1969-07-28 1971-02-18 Euratom Vorrichtung zur Ermittlung des Abbrands von Brennelementen eines Kernreaktors
ZA831467B (en) * 1982-03-25 1984-03-28 Westinghouse Electric Corp Measuring nuclear fuel burn-up

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
RU2185667C1 (ru) * 2001-02-06 2002-07-20 Федеральное государственное унитарное предприятие "Сибирский химический комбинат" Способ и система контроля обогащения гексафторида урана

Also Published As

Publication number Publication date
BE716988A (GUID-C5D7CC26-194C-43D0-91A1-9AE8C70A9BFF.html) 1968-12-02
DE1614014A1 (de) 1970-06-18
NL6808660A (GUID-C5D7CC26-194C-43D0-91A1-9AE8C70A9BFF.html) 1968-12-23
DE1614014B2 (de) 1972-06-22
FR1570956A (GUID-C5D7CC26-194C-43D0-91A1-9AE8C70A9BFF.html) 1969-06-13

Similar Documents

Publication Publication Date Title
US3786256A (en) Method and apparatus for nuclear fuel assay with a neutron source and coincident fission neutron detectors
DE3430857C2 (GUID-C5D7CC26-194C-43D0-91A1-9AE8C70A9BFF.html)
US3222521A (en) Method and apparatus for measuring fissionable isotope concentration
EP4036608B1 (en) Method of monitoring the radionuclide content of radioactive waste
JPS6058427B2 (ja) 核分裂性燃料含量の測定方法
GB1426926A (en) Analysis utilizing neutron irradiation
GB1240235A (en) Method for the non-destructive assay of bulk nuclear reactor fuel and apparatus
DE3430859A1 (de) Vorrichtung zum bestimmen des spalt- und brutstoffgehaltes des veraschungsrueckstandes in einem behaelter
DE3028963A1 (de) Verfahren und einrichtung zum messen des feuchtegehalts von schuettgut
Gordus Quantitative non-destructive neutron activation analysis of silver in coins
Krinninger et al. Pulsed neutron method for non-destructive and simultaneous determination of the 235U and 239Pu contents of irradiated and non-irradiated reactor fuel elements
GB1431445A (en) Automated multiple sample processing for well type radioactivity counters
GB1252230A (GUID-C5D7CC26-194C-43D0-91A1-9AE8C70A9BFF.html)
GB1235324A (en) A method of and apparatus for determining the content of fissile material in fuel samples or fuel elements of nuclear reactors
US8729488B2 (en) Assaying of waste
Fleming et al. Precise determination of aluminum by instrumental neutron activation
RU2082156C1 (ru) Способ обнаружения делящихся материалов
US4515749A (en) Subcriticality measurement apparatus and method
Tunnicliffe et al. A Method for the Accurate Determination of Relative Initial Conversion Ratios
Hartwell et al. Pulser injection with subsequent removal-implementation and applications
US3321626A (en) Measuring apparatus
Mantel et al. Isotopic analysis of uranium by neutron activation and high resolution gamma ray spectrometry
US3388254A (en) Method for determining the amount of cesium-137 in irradiated nuclear fuel
Dudey et al. FLUX-CHARACTERIZATION AND NEUTRON-CROSS-SECTION STUDIES IN EBR-II.
GB973322A (en) Method of and equipment for the non-destructive testing of steel products