DE2518877C3 - Method for determining the burn-up of nuclear fuel in fuel rod tubes and / or fuel assemblies - Google Patents
Method for determining the burn-up of nuclear fuel in fuel rod tubes and / or fuel assembliesInfo
- Publication number
- DE2518877C3 DE2518877C3 DE2518877A DE2518877A DE2518877C3 DE 2518877 C3 DE2518877 C3 DE 2518877C3 DE 2518877 A DE2518877 A DE 2518877A DE 2518877 A DE2518877 A DE 2518877A DE 2518877 C3 DE2518877 C3 DE 2518877C3
- Authority
- DE
- Germany
- Prior art keywords
- fuel
- burn
- determining
- isotope
- nuclear
- 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
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)
- Analysing Materials By The Use Of Radiation (AREA)
- Other Investigation Or Analysis Of Materials By Electrical Means (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Description
oder für die Flußzeitor for the river time
1010 Φ Τ =Φ Τ =
Cr50 Cr50 Cr 50 Cr 50
In -^52- (O) - In -^33- (Γ)In - ^ 52 - (O) - In - ^ 33 - (Γ)
Die Erfindung bezieht sich auf ein Verfahren zur Abbrandbestimmung von in Brennstabhüllrohren und/ oder Brennelementkästen befindlichen Kernbrennstoffen durch Messung der durch die Neutronenbestrahlung hervorgerufenen Verschiebung der Isotopenkonzentration eines Elementes mit einem Massenspektrometer.The invention relates to a method for determining the burn-up of fuel rod cladding tubes and / or fuel assemblies located nuclear fuel by measuring the neutron radiation caused shift of the isotope concentration of an element with a mass spectrometer.
Bei diesem etwa aus »Kernenergie«, 16. Jahrg. (1973), Seiten 362 bis 369 bekannten Verfahren wird der Urangehalt oder der Gehalt an Spaltprodukten massenspektrometrisch durch Messung der Isotopenverschiebung im Brennstoff bestimmt. Eine solche Messung ist jedoch nur durch Zerstörung der Brennstabhüllrohre bzw. Brennelementenkästen möglich.In this example from »Nuclear Energy«, 16th year (1973), Pages 362 to 369 known method is the uranium content or the content of fission products Determined by mass spectrometry by measuring the isotope shift in the fuel. Such However, measurement is only possible by destroying the fuel rod cladding tubes or fuel assembly boxes.
Aufgabe der Erfindung ist es, das eingangs angeführte Verfahren zu vereinfachen.The object of the invention is to simplify the method mentioned at the beginning.
Dies wird erfindungsgemäß dadurch erreicht, daß die Verschiebung der Isotopenkonzentration eines im Hüllrohr- und/oder Kastenmaterial enthaltenden Elements gemessen wird. Es hat sich überraschend gezeigt, daß das erfindungsgemäße, wesentlich vereinfachte Verfahren genaueste und den bisher bekannten Verfahren gleichwertige Ergebnisse liefert.This is achieved according to the invention in that the shift in the isotope concentration of an im Cladding tube and / or box material containing element is measured. It has surprisingly been shown that the inventive, much simplified method most accurate and the previously known Procedure delivers equivalent results.
Bekanntlich gilt für den Abbrand bu die folgende Beziehung:As is well known, the following relationship applies to the burnup bu:
bu = (I - e"' ■*'')■ 100% fifo bu = (I - e "'■ *'') ■ 100% fifo
(Spaltungen pro ursprünglich eingesetzter spaltbarer Atome).(Fissures per originally used fissile atoms).
Dabei ist örder Spaltwirkungsquerschnitt.Here ör is the gap cross section.
Die als Flußzeit bezeichnete Größe ΦΤ ist das Integral des Neutronenflusses über der Zeit, \y£w The quantity ΦΤ, called the flow time, is the integral of the neutron flow over time, \ y £ w
o50 bzw. o52 stellen geeignete, über das Reaktorspektrum gemittelte, totale Reaktionsquerschnitte für die entsprechenden Cr-Isotope dar.o 50 and o 52 represent suitable total reaction cross-sections averaged over the reactor spectrum for the corresponding Cr isotopes.
Liegen zwei stabile Isotope nebeneinander wie etwa Ni" und Ni*', Cr*2 und Cr" oder Fe5* und Fe'', so wird das zweite Isotop aus dem ersten durch Absorption eines Neutrons gebildet, alsoIf two stable isotopes lie next to one another, such as Ni "and Ni * ', Cr * 2 and Cr" or Fe 5 * and Fe ", the second isotope is formed from the first by the absorption of a neutron, i.e.
20 Fe56 (η, γ) Fc57. 20 Fe 56 (η, γ) Fc 57 .
Es gelten dann folgende Gleichungen:
Fc5" (r) = Fe56IO)C""5**1 The following equations then apply:
Fc 5 "(r) = Fe 56 IO) C"" 5 ** 1
undand
-~~ = Fe5h (/) «5h Φ - Fe57 α57 Φ . M d/- ~~ = Fe 5h (/) « 5h Φ - Fe 57 α 57 Φ. M d /
φ Τ = φ Τ =
ΦU)dt .ΦU) dt.
wobei Φ^είηεη Mittelwert darstellt.where Φ ^ είηεη represents mean value.
Bei hohen Abbränden wie sie vor allem bei schnellen Brutreaktoren geplant sind, treten Verschiebungen in den Isotopenverhältnissen der Metallatome des Hüllrohr- und/oder Kastenmaterials auf, die durch die unterschiedlich starke Absorption von Neutronen einzelner Isotope wie etwa Cr50 und Cr52 oder Ni62 und Ni64 hervorgerufen werden.In the case of high burn-ups, such as those planned especially for fast breeder reactors, shifts occur in the isotope ratios of the metal atoms of the cladding tube and / or box material, which are caused by the different strengths of absorption of neutrons of individual isotopes such as Cr 50 and Cr 52 or Ni 62 and Ni 64 are caused.
Für die Änderung der Isotopenkonzentrationen gilt näherungsweiseThe following applies approximately to the change in isotope concentrations
Cr50Ii) = Cr511IO)C""""'
Cr52If) = Cr52IO)C ""*'.Cr 50 Ii) = Cr 511 IO) C """"'
Cr 52 If) = Cr 52 IO) C "" * '.
Eine Messung der Flußzeit, der die bestrahlten Brennelemente ausgesetzt waren, ist nun sehr leicht möglich. Bei der Entladung der Brennelemente nimmtIt is now very easy to measure the flow time to which the irradiated fuel elements were exposed possible. When the fuel assemblies are discharged, it increases
bo man eine oberflächliche Probe des Hüllrohr- bzw. Kastenmaterials, die durch Abstriche mit einem rauhen Probenehmer erhalten werden kann und bringt diese Probe in einen Massenspektrographen mit welchem man Isotopenverhältnisse auf etwa 0,01% genau bestimmen kann. Bei den heute bereits erzielten Flußzeiten von 1022 n/cm2 genügt ein Unterschied in den Wirkungsquerschnitten von weniger als 10-24cm2, um Messungen der Flußzeit zu ermöglichen.bo a superficial sample of the cladding tube or box material, which can be obtained by smearing with a rough sampler, and this sample is placed in a mass spectrograph with which isotope ratios can be determined with an accuracy of about 0.01%. In the already achieved today Flußzeiten of 10 22 n / cm 2, a difference in the cross sections of less than 10 24 cm 2 is sufficient to enable measurement of the flow time.
Claims (1)
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
AT359574A AT333391B (en) | 1974-04-30 | 1974-04-30 | METHOD FOR MEASURING THE LOCAL FLOW TIME AND THE COMBUSTION OF NUCLEAR FUELS IN FUEL PIPES AND / OR FUEL ELEMENT BOX |
Publications (3)
Publication Number | Publication Date |
---|---|
DE2518877A1 DE2518877A1 (en) | 1975-11-13 |
DE2518877B2 DE2518877B2 (en) | 1979-03-15 |
DE2518877C3 true DE2518877C3 (en) | 1979-11-08 |
Family
ID=3552690
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
DE2518877A Expired DE2518877C3 (en) | 1974-04-30 | 1975-04-28 | Method for determining the burn-up of nuclear fuel in fuel rod tubes and / or fuel assemblies |
Country Status (2)
Country | Link |
---|---|
AT (1) | AT333391B (en) |
DE (1) | DE2518877C3 (en) |
-
1974
- 1974-04-30 AT AT359574A patent/AT333391B/en not_active IP Right Cessation
-
1975
- 1975-04-28 DE DE2518877A patent/DE2518877C3/en not_active Expired
Also Published As
Publication number | Publication date |
---|---|
AT333391B (en) | 1976-11-25 |
DE2518877A1 (en) | 1975-11-13 |
ATA359574A (en) | 1976-03-15 |
DE2518877B2 (en) | 1979-03-15 |
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Legal Events
Date | Code | Title | Description |
---|---|---|---|
C3 | Grant after two publication steps (3rd publication) | ||
8328 | Change in the person/name/address of the agent |
Free format text: MEHL, E., DIPL.-ING., PAT.-ANW., 8000 MUENCHEN |
|
8339 | Ceased/non-payment of the annual fee |