PL109438B1 - Method of determining content of fissionable elements,specially uranium-235 in reactor fuel elements - Google Patents
Method of determining content of fissionable elements,specially uranium-235 in reactor fuel elements Download PDFInfo
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- PL109438B1 PL109438B1 PL1976186441A PL18644176A PL109438B1 PL 109438 B1 PL109438 B1 PL 109438B1 PL 1976186441 A PL1976186441 A PL 1976186441A PL 18644176 A PL18644176 A PL 18644176A PL 109438 B1 PL109438 B1 PL 109438B1
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- 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
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Description
Przedmiotem wynalazku jest sposób oznaczania zawartosci pierwiastków rozszczepialnych, zwlasz¬ cza uranu — 235 w reaktorowych elementach pa¬ liwowych, szczególnie przydatny w procesach zwia¬ zanych z miedzynarodowa kontrola w ramach U- kladu o Nierozprzestrzenianiu Broni Jadrowej o- raz przy optymalizacji wykorzystania paliwa w e- nergetycznych reaktorach jadrowych.The subject of the invention is a method for determining the content of fissile elements, especially uranium - 235 in reactor fuel elements, particularly useful in processes related to international control under the Non-Proliferation of Nuclear Weapons System and optimizing the use of fuel in - nuclear power reactors.
Znany stan techniki. Znane sposoby oznaczania zawartosci uranu-235 w reaktorowych elementach paliwowych polegaja na stosowaniu takich metod jak neutronografia, gamma Scanning, metoda neu¬ tronów opóznionych i metoda stalego okresu.The known state of the art. Known methods of determining the uranium-235 content in reactor fuel elements include the use of methods such as neutronography, gamma scanning, the lagged neutron method and the fixed period method.
Sposób oznaczania zawartosci pierwiastków roz¬ szczepialnych w reaktorowych elementach oparty w metodzie stalego okresu polega na tym, ze mie¬ rzy sie staly okres reaktora jadrowego z elemen¬ tem paliwowym badanym, a nastepnie w tych sa¬ mych warunkach fizycznych dokonuje sie pomia¬ ru stalego okresu reaktora z elementem paliwo¬ wym wzorcowym o znanej zawartosci pierwiast¬ ka rozszczepialnego, przykladowo uranu — 235, po czym wyznacza sie róznice wartosci tych okresów, która jest miara zawartosci pierwiastka rozszcze¬ pialnego w badanym elemencie paliwowym.The method of determining the content of dissolving elements in reactor elements based on the fixed period method consists in measuring the constant period of the nuclear reactor with the fuel element under test, and then under the same physical conditions a constant measurement is performed period of the reactor with a standard fuel element with a known content of a fissile element, for example uranium-235, and then the differences in the values of these periods are determined, which is a measure of the content of the fissile element in the tested fuel element.
Opisany sposób wykorzystujacy prawa dynamiki reaktorów wymaga pracochlonnej i skomplikowa¬ nej kalibracji ukladu pomiarowego i obróbki uzy¬ skanych wyników. 10 15 20 25 Istota wynalazku. Sposób oznaczania zawartosci pierwiastków rozszczepialnych w reaktorowych e- lementach paliwowych wedlug wynalazku polega na tym, ze mierzy sie polozenie elementu regula¬ cyjnego w stanie ustalonego poziomu mocy reak¬ tora z badanym elementem paliwowym. Nastep¬ nie dokonuje sie pomiaru polozenia elementu re¬ gulacyjnego w tych samych warunkach fizycznych z elementem wzorcowym o znanej zawartosci pier¬ wiastka rozszczepialnego, po czym wyznacza sie róznice wartosci tych polozen, która jest miara zawartosci pierwiastka rozszczepialnego w bada¬ nym elemencie paliwowym. Polozenie elementu re¬ gulacyjnego cechuje sie za pomoca jednego lub kilku wzorcowych elementów paliwowych przez co uzyskuje sie charakterystyke polozenia elementu regulacyjnego w funkcji zawartosci pierwiastka rozszczepialnego.The described method using the laws of dynamics of reactors requires a laborious and complicated calibration of the measuring system and the processing of the obtained results. Summary of the invention. The method of determining the content of fissile elements in reactor fuel elements according to the invention consists in measuring the position of the regulating element in a state of a steady power level of the reactor with the fuel element under test. Then, the position of the control element is measured under the same physical conditions with a standard element with a known fissile element content, and the differences in the values of these positions are determined, which is a measure of the fissile element content in the tested fuel element. The position of the regulating element is characterized by one or more reference fuel elements, which gives the characteristics of the position of the regulating element as a function of the content of the fissile element.
Korzystne skutki techniczne wynalazku. Sposób wedlug wynalazku w odróznieniu od znanego spo¬ sobu opartego na metodzie stalego okresu, oparty jest na prawach statyki reaktorów jadrowych i nie wymaga zadnej matematycznej obróbki uzys¬ kanych wyników gdyz polozenie elementu regu¬ lacyjnego dostarcza bezposrednio informacji o za¬ wartosci pierwiastka rozszczepialnego w badanym elemencie paliwowym.Advantageous technical effects of the invention. The method according to the invention, unlike the known method based on the fixed period method, is based on the laws of statics of nuclear reactors and does not require any mathematical processing of the obtained results, because the position of the regulating element provides directly information about the content of the fissile element in the tested fuel element.
Przyklad wykonania wynalazku.Example of an embodiment of the invention.
Oznaczanie zawartosci uranu-235 w reaktoro- 109 4383 109 438 4 wym elemencie paliwowym. Do kanalu w rdzeniu reaktora wprowadza sie wzorcowy element pali¬ wowy Ewl o znanej zawartosci uranu-235, dopro¬ wadza sie reaktor do stanu krytycznego i stabili¬ zuje sie jego moc a nastepnie odczytuje sie polo¬ zenie elementu regulacyjnego pi przy stalym po¬ lozeniu elementu kompensacyjnego i pozostalych elementów regulacyjnych. Na miejsce elementu Ewi wprowadza sie element wzorcowy Ew2 o zna¬ nej zawartosci uranu-235 i po ustaleniu sie polozenia elementu regulacyjnego Pt odczytuje sie jego polozenie P2. W ten sam sposób skaluje sie caly element regulacyjny w jednostkach wago¬ wych uranu — 235 zawartego w elementach wzor¬ cowych. Nastepnie przy srodkowym polozeniu ele¬ mentu regulacyjnego Pj w ten sam sposób skaluje sie element kompensacyjny. Po tych czynnosciach do kanalu rdzenia reaktora wprowadza sie ele¬ ment badany Ex i stabilizuje sie moc reaktora.Determination of uranium-235 content in the reactor-109 4383 109 438 4 fuel element. The standard fuel element Ewl with a known content of uranium-235 is introduced into the channel in the reactor core, the reactor is brought to a critical state and its power is stabilized, and then the position of the control element pi is read at a fixed position. the compensating element and other adjusting elements. In place of the element Ewi, the reference element Ew2 with a known content of uranium-235 is inserted, and after the position of the control element Pt is established, its position P2 is read. In the same manner, the entire control element is scaled in weight units of the uranium 235 contained in the reference elements. The compensating element is then scaled in the same way at the central position of the control element Pj. After these activities, the tested element Ex is introduced into the channel of the reactor core and the reactor power is stabilized.
Miara zawartosci uranu — 235 w badanym ele¬ mencie paliwowym Ex sa polozenia elementu re¬ gulacyjnego Pa i elementu kompensacyjnego. Tak wiec zawartosc U-235 w Ex = kiPa + k2Pk gdzie kj i k2 sa wspólczynnikami proporcjonal¬ nosci a znak wspólczynnika kj zalezy od poloze¬ nia elementu regulacyjnego wzgledem jego po¬ lozenia srodkowego. W przypadku wyznaczania róznicy zawartosci uranu — 235 miedzy elemen¬ tem wzorcowym Ew i elementem badanym Ex, dokladnosc pomiarów jest jeszcze lepsza gdyz w tym przypadku element kompensacyjny nie zmie¬ nia swego polozenia, a róznica zawartosci U-235 w elemencie badanym Ex w porównaniu z ele¬ mentem wzorcowym Ew bedzie: Róznica zawartosci k-235 = kiPa, a calkowita zawartosc U-235 w Ex = Pa + zawartosc U-235 w Ew.The measure of uranium content - 235 in the tested fuel element Ex are the positions of the control element Pa and the compensating element. Thus, the U-235 content in Ex = kiPa + k2Pk where kj and k2 are proportional coefficients and the sign of the kj factor depends on the position of the control element with respect to its middle position. In the case of determining the difference in uranium content - 235 between the standard element Ew and the tested element Ex, the accuracy of the measurements is even better, because in this case the compensating element does not change its position, and the difference in the content of U-235 in the tested element Ex compared to The reference element Ew will be: The difference in the content of k-235 = kPa, and the total content of U-235 in Ex = Pa + the content of U-235 in Ew.
Za,strzezenia patentowe 1. Sposób oznaczania zawartosci pierwiastków rozszczepialnych w reaktorowych elementach pa¬ liwowych, znamienny tym, ze w reaktorze w sta¬ nie krytycznym mierzy sie polozenie elementu re¬ gulacyjnego w stanie ustalonego poziomu mocy reaktora z badanym elementem paliwowym a na¬ stepnie dokonuje sie pomiaru polozenia elementu regulacyjnego w tych samych warunkach fizycz¬ nych z elementem wzorcowym o znanej zawartos¬ ci pierwiastka rozszczepialnego, po czym wyzna¬ cza sie róznice wartosci tych polozen, która jest miara zawartosci pierwiastka rozszczepialnego w badanym elemencie paliwowym. 2. Sposób wedlug zastrz. 1, znamienny tym, ze polozenie elementu regulacyjnego cechuje sie za pomoca jednego lub kilku paliwowych elemen¬ tów wzorcowych przez co uzyskuje sie charak¬ terystyke polozenia elementu regulacyjnego w funkcji zawartosci pierwiastka rozszczepialnego. 10 15 20 29 DN-3, zam. 828/80 Cena 45 xlPatent claims 1. The method of determining the content of fissile elements in reactor fuel elements, characterized in that in a reactor in a critical state, the position of the control element is measured in the state of a steady power level of the reactor with the tested fuel element, and then the position of the control element is measured under the same physical conditions with a standard element with a known fissile element content, and then the differences in the values of these positions are determined, which is a measure of the fissile element content in the tested fuel element. 2. The method according to claim The method according to claim 1, characterized in that the position of the control element is characterized by one or more fuel reference elements, which gives the characteristics of the control element position as a function of the fissile element content. 10 15 20 29 DN-3, order. 828/80 Price 45 xl
Priority Applications (1)
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PL1976186441A PL109438B1 (en) | 1976-01-09 | 1976-01-09 | Method of determining content of fissionable elements,specially uranium-235 in reactor fuel elements |
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PL1976186441A PL109438B1 (en) | 1976-01-09 | 1976-01-09 | Method of determining content of fissionable elements,specially uranium-235 in reactor fuel elements |
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PL109438B1 true PL109438B1 (en) | 1980-05-31 |
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1976
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