[go: up one dir, main page]

GB1248030A - Apparatus for measuring the content of fissile substance of fuel elements or the burn-up of fuel elements, of a nuclear reactor - Google Patents

Apparatus for measuring the content of fissile substance of fuel elements or the burn-up of fuel elements, of a nuclear reactor

Info

Publication number
GB1248030A
GB1248030A GB35809/70A GB3580970A GB1248030A GB 1248030 A GB1248030 A GB 1248030A GB 35809/70 A GB35809/70 A GB 35809/70A GB 3580970 A GB3580970 A GB 3580970A GB 1248030 A GB1248030 A GB 1248030A
Authority
GB
United Kingdom
Prior art keywords
elements
fuel elements
content
neutron
fissile
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
GB35809/70A
Inventor
Ronald Dierckx
Walter Hage
Siegfried Kumpf
Victor Raievski
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.)
European Atomic Energy Community Euratom
Original Assignee
European Atomic Energy Community Euratom
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 European Atomic Energy Community Euratom filed Critical European Atomic Energy Community Euratom
Publication of GB1248030A publication Critical patent/GB1248030A/en
Expired legal-status Critical Current

Links

Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C1/00—Reactor types
    • G21C1/04—Thermal reactors ; Epithermal reactors
    • G21C1/06—Heterogeneous reactors, i.e. in which fuel and moderator are separated
    • G21C1/07—Pebble-bed reactors; Reactors with granular fuel
    • 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)

Abstract

1,248,030. Fuel elements. EUROPEAN ATOMIC ENERGY COMMUNITY. 23 July, 1970 [28 July, 1969], No. 35809/70. Heading G6C. The fissile content of nuclear fuel elements is measured by removing the elements from the reactor, storing the elements for an interval until the slow neutrons are emitted, irradiating the elements with the reactor neutron flux and then detecting the neutrons emitted which provides a measure of the fissile material content. Fuel element spheres from the core 1, are moved into the tube 3 for 15 minutes, where slow neutron emission occurs and then pass into the shield 4 where they are exposed to reactor neutron irradiation at 5. The neutron spectrum may be selected by filters. After a further period, the elements pass into the neutron detector 6 where the fissile content is estimated.
GB35809/70A 1969-07-28 1970-07-23 Apparatus for measuring the content of fissile substance of fuel elements or the burn-up of fuel elements, of a nuclear reactor Expired GB1248030A (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
DE19691938836 DE1938836A1 (en) 1969-07-28 1969-07-28 Device for determining the burn-up of fuel elements in a nuclear reactor

Publications (1)

Publication Number Publication Date
GB1248030A true GB1248030A (en) 1971-09-29

Family

ID=5741416

Family Applications (1)

Application Number Title Priority Date Filing Date
GB35809/70A Expired GB1248030A (en) 1969-07-28 1970-07-23 Apparatus for measuring the content of fissile substance of fuel elements or the burn-up of fuel elements, of a nuclear reactor

Country Status (6)

Country Link
BE (1) BE753527A (en)
DE (1) DE1938836A1 (en)
FR (1) FR2053208B1 (en)
GB (1) GB1248030A (en)
LU (1) LU61287A1 (en)
NL (1) NL7010094A (en)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN115295189A (en) * 2022-08-15 2022-11-04 清华大学 Burnup measuring calibration positioner for pebble-bed high-temperature reactor
CN116844665A (en) * 2023-03-23 2023-10-03 上海交通大学 Energy spectrum filtering system in ultra-plutonium isotope production

Families Citing this family (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2248807B1 (en) * 1973-10-26 1976-12-31 Rinnai Kk
DE3437121C2 (en) * 1984-10-10 1987-04-23 Liebing, geb. Wittig, Barbara, 7303 Neuhausen Hybrid control for pressure cookers
DE19941719C2 (en) * 1999-09-02 2003-12-04 Forschungszentrum Juelich Gmbh Process for removing spent fuel from a high temperature pebble bed reactor

Family Cites Families (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
GB1235324A (en) * 1967-06-22 1971-06-09 Kernforschungsanlage Juelich A method of and apparatus for determining the content of fissile material in fuel samples or fuel elements of nuclear reactors

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN115295189A (en) * 2022-08-15 2022-11-04 清华大学 Burnup measuring calibration positioner for pebble-bed high-temperature reactor
CN116844665A (en) * 2023-03-23 2023-10-03 上海交通大学 Energy spectrum filtering system in ultra-plutonium isotope production
CN116844665B (en) * 2023-03-23 2024-03-01 上海交通大学 Energy spectrum filtering system in production of plutonium isotopes

Also Published As

Publication number Publication date
DE1938836A1 (en) 1971-02-18
NL7010094A (en) 1971-02-01
FR2053208A1 (en) 1971-04-16
FR2053208B1 (en) 1973-12-21
BE753527A (en) 1970-12-31
LU61287A1 (en) 1970-09-10

Similar Documents

Publication Publication Date Title
GB1168198A (en) Detection, Identification and Analysis of Fissionable Isotopes
GB923083A (en) Improvements in/or relating to the monitoring of fission products in a gaseous stream, particularly for detecting burst slugs in nuclear reactors
US3728544A (en) Method and apparatus for measurement of concentration of thermal neutron absorber contained in nuclear fuel
GB1252230A (en)
GB1248030A (en) Apparatus for measuring the content of fissile substance of fuel elements or the burn-up of fuel elements, of a nuclear reactor
GB1526719A (en) Apparatus and method for detecting power distribution in a nuclear reactor fuel element
US4881247A (en) Measuring nuclear fuel burnup
JPS5493795A (en) Concentration mesearing method and device of neutron strong absorbent in fuel rod
Johnston et al. The thermal neutron absorption cross-section of 233Th and the resonance integrals of 232Th, 233Th and 59Co
GB917776A (en) Method of measuring the amount of material fissile by thermal neutrons and present in any arbitrary substance, particularly for controlling the state of exhaustion of fuel elements in nuclear reactors
GB817752A (en) Nuclear chain reacting systems
GB1197099A (en) Method and device for the Non-Destructive Control of Nuclear Fuels
Blosser et al. NEUTRON FLUX AND NEUTRON AND GAMMA-RAY SPECTRA MEASUREMENTS AT THE HFIR.
Choppin et al. Prompt Neutrons from the Spontaneous Fission of Fermium-254
GB836147A (en) Improvements in or relating to shielding for nuclear reactors
JPS54151795A (en) Measuring degree of burning of nuclear fuel
Topp 236Pu Contaminant in 238Pu Produced in Power Reactors
Duwe et al. Measurements to distinguish fuel elements with and without thorium content by gammaspectrometry in hot cells
Souza et al. Thermal neutron flux measurements in the rotary specimen rack of the IPR-R1 TRIGA reactor
Johansson A measurement of the prompt fission neutron spectrum of U-235 at 0.5 MeV incident neutron energy
Alfassi Use of delayed neutrons in activation analysis
Rozain et al. SILENE, a new radiation reference source
Strindehag et al. Aktiebolaget Atomenergi
Bonyushkan et al. Fragment yield in the fission of U233 and Pu239 by fast neutrons
Dessauer et al. Photographic neutron dosimetry to date