WO2005068544A2 - Radiation protection material - Google Patents
Radiation protection material Download PDFInfo
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- WO2005068544A2 WO2005068544A2 PCT/EP2005/050156 EP2005050156W WO2005068544A2 WO 2005068544 A2 WO2005068544 A2 WO 2005068544A2 EP 2005050156 W EP2005050156 W EP 2005050156W WO 2005068544 A2 WO2005068544 A2 WO 2005068544A2
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- radiation protection
- protection material
- radiation
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
- G21F1/00—Shielding characterised by the composition of the materials
- G21F1/02—Selection of uniform shielding materials
- G21F1/10—Organic substances; Dispersions in organic carriers
- G21F1/103—Dispersions in organic carriers
- G21F1/106—Dispersions in organic carriers metallic dispersions
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
- G21F1/00—Shielding characterised by the composition of the materials
- G21F1/12—Laminated shielding materials
- G21F1/125—Laminated shielding materials comprising metals
Definitions
- the invention relates to a radiation protection material made of an elastomer or plastomer as a matrix material into which elements with an atomic number greater than 50 or their connections are incorporated as radiation-absorbing materials.
- DE 19955192 discloses a production method for radiation protection materials in which elements of an atomic number greater than 50 or compounds with these elements are used as radiation-absorbing materials; tin is provided as an essential component. Because of its ductility, this tin requires a special manufacturing process, which is described there, since the tin particles are formed into platelets during the process, so that the material with the radiation-absorbing material must be extracted to ensure the desired properties. Such a procedure is complex, so that economically viable production is questioned. To achieve defined lead equivalents, DE 10234158 specifies compositions containing tin, the manufacture of which does not deal with the aforementioned problem with tin powder. Thus, the object of the invention is to provide a radiation protection material with which reliable radiation absorption is achieved and which is economical to manufacture and easy to process.
- the radiation protection material is composed of a matrix material based on a natural or synthetic rubber, into which antimony powder, mixed with alkaline earth tungstates (in the form of calcium tungstate) with a content of 64 wt. tungsten as an additive I and oxides, carbonates or other inorganic compounds of elements of the lanthanide series, such as gadolinium oxide with a content of 86.7 gevi, gadolinium or cerium carbonate with a content of 82.4 wt.% cerium as additive II, is uniformly incorporated.
- This plastic mixture obtained in this way is then pulled to the film, from which radiation protection aprons or other radiation protection clothing are then assembled.
- the advantage here is a structure with a matrix that lies in the range from 5 to 20 percent.
- the radiation-absorbing additives are worked into the material of this matrix. Such are considered: antimony with 0 - 82 Gew2, bismuth with 0 - 40 Gewx, Gadolinium with 0 - 20 GewX. Wol fram with 0 - 30 weight and cerium with 0 - 10 weight.
- such a material has the following composition:
- multi-layer systems can also be used. It has surprisingly been found that in such multilayer systems the attenuation equivalents of the individual layers are not additively linked and at least in areas up to 100 kV are significantly above the additive values.
- the following visual attenuation equivalents were measured in the narrow radiation bundle with filtering for normal radiation using an: attenuation equivalents according to EN6133-1 at 60 kV at 80 kV at 100 kV at 125 mm Pb mm Pb mn Pb mm Pb
- the measured values in the diagnostically interesting range below 120 kV are significantly larger than the additive values, so that the desired radiation attenuation is achieved with a smaller thickness and thus with a lower weight of the radiation protection clothing made from it.
- other additives with a large neutron absorption cross section - for example boron or boron compounds - can also be used.
- the selection of such additives must take into account how these additives can be taken up by the matrix material and mixed into them, whereby the wettability of these additives by the matrix material must be taken into account.
- This film which is made from a radiation protection material based on an elastomer matrix, is suitable for producing a material for radiation protection clothing, such as aprons.
- a material for radiation protection clothing such as aprons.
- multi-layer materials are also used, the same foils being used in several layers.
- the higher attenuation equivalents of the combination which are higher than the simple addition of the individual attenuation equivalents, allow a reduction in the thickness of the material for the radiation protective clothing and thus also its surface weight.
Abstract
The invention relates to a lead-free radiation protection material which is made of elastomer or a plastomer as matrix material wherein elements having an atomic number greater than 50 or compounds thereof are incorporated as radiation-absorbing materials. The aim of the invention is to improve said radiation protection material in such a manner that safe radiation absorption can be achieved and that it can be produced in an economical manner and that it is simple to process. As a result, the radiation-absorbing materials are made of a combination of antimony and bismuth. Said materials can also be made of tungsten and/or elements from the rare earth group.
Description
Strahlenschutzmaterial Radiation protection material
Die Erfindung betrifft ein Strahlenschutzmaterial aus einem Elastomer oder Plastomer als Matrixmaterial in das als Strahlungsabsorbierende Materialien Elemente mit einer Ordnungszahl größer 50 oder deren Verbindungen eingearbeitet sind.The invention relates to a radiation protection material made of an elastomer or plastomer as a matrix material into which elements with an atomic number greater than 50 or their connections are incorporated as radiation-absorbing materials.
Aus DE 19955192 ist eine Herstellungsweise für Strahlenschutzmaterialien bekannt, bei der als Strahlungsabsorbierende Materialien Elemente einer Ordnungszahl größer 50 oder Verbindungen mit diesen Elementen eingesetzt sind; als wesentlicher Bestandteil ist dort Zinn vorgesehen. Dieses Zinn erfordert aufgrund seiner Duktilität ein besonderes, dort beschriebenes Herstellungsverfahren, da beim Prozess die Zinnpart el zu Plättchen umgeformt werden, so dass das mit dem Strahlungsabsorbierenden Material versetzte unststoffaterial ge- strainert werden muss, um die gewünschten Eigenschaften sicher zu stellen. Ein solches Vorgehen ist aufwendig, so dass eine wirtschaftlich tragbare Herstellung in Frage gestellt ist. Zum Erreichen definierter Bleigleichwerte gibt die DE 10234158 zinnhaltige Zusammensetzungen an, bei deren Herstellung mit Zinnpulver die vorerwähnte Problematik nicht zu umgehen ist.
Somit stellt sich der Erfindung die Aufgabe, ein Strahlenschutzmaterial anzugeben, mit dem eine sichere Strahlungsabsorption erreicht wi d, und das wi tschaftlich herzustellen und einfach zu verarbeiten ist.DE 19955192 discloses a production method for radiation protection materials in which elements of an atomic number greater than 50 or compounds with these elements are used as radiation-absorbing materials; tin is provided as an essential component. Because of its ductility, this tin requires a special manufacturing process, which is described there, since the tin particles are formed into platelets during the process, so that the material with the radiation-absorbing material must be extracted to ensure the desired properties. Such a procedure is complex, so that economically viable production is questioned. To achieve defined lead equivalents, DE 10234158 specifies compositions containing tin, the manufacture of which does not deal with the aforementioned problem with tin powder. Thus, the object of the invention is to provide a radiation protection material with which reliable radiation absorption is achieved and which is economical to manufacture and easy to process.
Diese Aufgabenstellung wird durch die im unabhängigen Anspruch 1 aufgeführten Merkmale gelöst; vorteilhafte Weiterbildungen und bevorzugte Ausführungsformen beschreiben die Unteransprüche.This task is solved by the features listed in independent claim 1; advantageous further developments and preferred embodiments describe the subclaims.
Durch den Ersatz des Zinn durch Antimon lassen sich gegenüber der Röntgenstrahlung einer mit einer Spannung im Bereich von 4o kV bis 125 kV liegenden Betriebsspannung betriebenen Röntgenröhre Absorptionswerte erzielen, die im Wesentlichen die gleichen sind, wie sie mit Zinn erreicht werden. Daher kann es mit diesen auf Antimon umgestellten Materalien in überraschender Weise zu einer wesentlichen Vereinfachung des Herstellungsprozesses führen: Das Strainern entfällt, da sich Antimonpartkel während der Verarbeitung nicht zu Plättchen umformen. Dies führt damit zu einer einfacheren und somit wirtschaftlicheren Herstellung, wobei die Absorptionseigenschaften des Antimon denen des Zinns entsprechen. Die Zusätze von Bismut, seltene Erden wie beispielsweise Gadolinum oder Cer sowie von Wolfram helfen mit, bei Antimon vorkommende Absorptionslücken zu schl eßen.By replacing the tin with antimony, absorption values can be achieved compared to the X-rays of an X-ray tube operated with a voltage in the range from 40 kV to 125 kV, which are essentially the same as those achieved with tin. Therefore, with these materials converted to antimony, it can surprisingly lead to a significant simplification of the manufacturing process: the straining is not necessary since antimony particles do not form into platelets during processing. This leads to a simpler and therefore more economical production, the absorption properties of the antimony corresponding to those of the tin. The addition of bismuth, rare earths such as gadolinum or cerium and tungsten help to close absorption gaps that occur with antimony.
So lassen sich Strahlenschutzmaterialien herstellen, die den in DE 199 55192 beschriebenen Strahlenschutzmaterialien entsprechen und diesen in ihren Absorptionseigenschaften nicht nachstehen; beispielsweise ist das Strahlenschutzmaterial mit einem Matrixmaterial auf der Basis eines Natur- oder eines Synthesekautschuks aufgebaut, in das Antimonpulver, versetzt mit Erdalkaliwolframate (in Form von Calziumwolframat) mit einem Gehalt von 64 Gew£ Wolfram als ein Zuschlagstoff I und Oxide, Carbo- nate oder andere anorganische Verbindungen von Elementen der Lanthanoi- den-Reihe, etwa Gadolinium-Oxid mit einem Gehalt 86,7 Gevi , Gadoliniumoder Cercarbonat mit einem Gehalt von 82,4 Gew£ Cer als Zuschlagstoff II, gleichförmig eingelagert ist. Dieses so gewonnene Kunststoffgemisch
wird anschließend zur Folie gezogen, aus der dann Strahl enschutzschürzen oder andere Strahlenschutzkleidungen konfektioniert werden.In this way, radiation protection materials can be produced which correspond to the radiation protection materials described in DE 199 55192 and which are not inferior in their absorption properties; for example, the radiation protection material is composed of a matrix material based on a natural or synthetic rubber, into which antimony powder, mixed with alkaline earth tungstates (in the form of calcium tungstate) with a content of 64 wt. tungsten as an additive I and oxides, carbonates or other inorganic compounds of elements of the lanthanide series, such as gadolinium oxide with a content of 86.7 gevi, gadolinium or cerium carbonate with a content of 82.4 wt.% cerium as additive II, is uniformly incorporated. This plastic mixture obtained in this way is then pulled to the film, from which radiation protection aprons or other radiation protection clothing are then assembled.
Dabei versteht es sich von selbst, dass auch in den zinnhaltigen Materialien nach dem Stand der Technik, etwa solche nach DE 199 55 192 oder DE 102 34 159, das in elementarer Form vorliegende Zinn durch Antimon ersetzt werden kann, wobei die auf die Masse bezogenen Gewichts- Prozent - angaben im Wesentlichen die Gleichen sind, wobei mit dem Ersatz von Zinn durch Antimon Materialien erreicht werden, mit denen identische Blei - gleichwerte mit dünneren Material stärken erreicht werden können .It goes without saying that even in the tin-containing materials according to the state of the art, for example those according to DE 199 55 192 or DE 102 34 159, the tin present in elemental form can be replaced by antimony, the weight-related ones The percentages by weight are essentially the same, but replacing tin with antimony gives materials with which identical lead equivalents can be achieved with thinner materials.
Vortei l haft i st dabei ein Aufbau mit einer Matrix, die im Bereich von 5 bis 20 Gevι% l iegt . In das Material dieser Matrix sind die strahl ungsabsobierenden Zusätze ei ngearbeitet . Al s solche kommen in Betracht : Antimon mit 0 - 82 Gew2, Bismut mit 0 - 40 Gewft, Gadoli nium mit 0 - 20 GewX. Wol fram mit 0 - 30 Gewft und Cer mit 0 - 10 Gew£.The advantage here is a structure with a matrix that lies in the range from 5 to 20 percent. The radiation-absorbing additives are worked into the material of this matrix. Such are considered: antimony with 0 - 82 Gew2, bismuth with 0 - 40 Gewx, Gadolinium with 0 - 20 GewX. Wol fram with 0 - 30 weight and cerium with 0 - 10 weight.
Vorteilhaft haben sich bewährt: Materi al AI Materi al A2 Material A3Have proven to be advantageous: Materi al AI Materi al A2 Material A3
Matrix: 10 - 20 Gew£ 12 - 18 Gew£ 12 - 14 Gew£Matrix: 10-20 pounds 12-18 pounds 12-14 pounds
Sb: 0 - 40 Gew£ 32 - 82 Gewft 60 - 80 Gew%Sb: 0 - 40 weight £ 32 - 82 weight 60 - 80 weight%
Bi : 0 - 32 Gew£ 0 - 30 Gew% 4 - 18 GewBi: 0 - 32 wt. £ 0 - 30 wt.% 4 - 18 wt
Gd/Ce: 0 - 18 Gew2 4 - 18 Gew2 8 - 17 Gew£Gd / Ce: 0 - 18 Gew2 4 - 18 Gew2 8 - 17 Gew £
W: 0 - 35 Gew2 0 - 27 Gew£ 9 - 18 Gew2W: 0 - 35 Gew2 0 - 27 Gew £ 9 - 18 Gew2
In bevorzugter Ausführung hat ein sol ches Material die folgende Zusa mensetzung:In a preferred embodiment, such a material has the following composition:
Matrix: 18,0 Gew£Matrix: 18.0 pounds
Sb: 30,0 Gew£Sb: 30.0 lbs
Bi : 35,0 Gew (als Oxid)Bi: 35.0 wt (as oxide)
Gd: 11,0 Gevι% (als Oxid)Gd: 11.0% (as oxide)
W: 7,0 Gew (als Oxid)W: 7.0 wt. (As oxide)
Ce: 5,0 Gevι% (als Oxid)
Dieses Material weist die Schwächungsgleichwerte nach folgender Tabelle auf:Ce: 5.0% by weight (as oxide) This material shows the weakening equivalents according to the following table:
Nenn-Blei- FlächenSchwäch ungsg' leichwerte nach EN6133-1Nominal lead FlächenSchwäch ungsg 'facilitated values to EN6133-1
Gl eichwert gewicht bei 60 kV bei 80 kV bei 100 kV bei 125 kV mm kg/m2 mm Pb mm Pb m Pb mm PbEqual value weight at 60 kV at 80 kV at 100 kV at 125 kV mm kg / m2 mm Pb mm Pb m Pb mm Pb
0,125 1,380 0,121 0,140 0,147 0,1380.125 1.380 0.121 0.140 0.147 0.138
0,250 2,900 0,258 0,289 0,304 0,2640.250 2.900 0.258 0.289 0.304 0.264
0,500 5,900 0,561 0,657 0,654 0,5450.500 5.900 0.561 0.657 0.654 0.545
Es versteht sich dabei von selbst, dass auch Mehrschicht-Systeme zum Einsatz kommen können. Dabei hat sich überraschender Weise gezeigt, dass in solchen Mehrschichten-Systemen die Schwächungsgleichwerte der einzelnen Schichten nicht additiv verknüpft sind und zumindest in Bereichen bis 100 kV deutlich über den additiven Werten liegen. So wurden folgende Sehwächungsgleichwerte im schmalen Strahlungsbündel mit Filterung für NormalStrahlung mit einer gemessen: Schwächungsgleichwerte nach EN6133-1 bei 60 kV bei 80 kV bei 100 kV bei 125 mm Pb mm Pb mn Pb mm PbIt goes without saying that multi-layer systems can also be used. It has surprisingly been found that in such multilayer systems the attenuation equivalents of the individual layers are not additively linked and at least in areas up to 100 kV are significantly above the additive values. The following visual attenuation equivalents were measured in the narrow radiation bundle with filtering for normal radiation using an: attenuation equivalents according to EN6133-1 at 60 kV at 80 kV at 100 kV at 125 mm Pb mm Pb mn Pb mm Pb
Ml 0,115 0,132 0,142 0,135Ml 0.115 0.132 0.142 0.135
Ml: 0,114 0,131 0,142 0,134Ml: 0.114 0.131 0.142 0.134
M2: 0,115 0,133 0,140 0,134M2: 0.115 0.133 0.140 0.134
Diese Folien wurden in den folgenden Kombinationen zusammengesetzt und entsprechend der vorherigen Messreihe durchgemessen; die ermittelten Werte sind den additiven Werten gegenüber (Additiver Wert/Messwert) gestellt: Schwächungsgleichwerte nach EN6133-1 bei 60 kV bei 80 kV bei 100 kV bei 125 kV m Pb mm Pb mm Pb mm PbThese foils were put together in the following combinations and measured according to the previous series of measurements; the determined values are compared with the additive values (additive value / measured value): attenuation equivalents according to EN6133-1 at 60 kV at 80 kV at 100 kV at 125 kV m Pb mm Pb mm Pb mm Pb
M2 + M3 0,229/0,249 0,264/0,287 0,282/0,288 0,269/0,258M2 + M3 0.229 / 0.249 0.264 / 0.287 0.282 / 0.288 0.269 / 0.258
M1+M2+M3 0,344/0,394 0,396/0,472 0,424/0,465 0,401/0,391M1 + M2 + M3 0.344 / 0.394 0.396 / 0.472 0.424 / 0.465 0.401 / 0.391
Die Messwerte sind dabei im diagnostisch interessierenden Bereich unter 120 kV deutlich größer als die additiven Werte, so dass die gewünschte Strahl ungsschwächung mit einer geringeren Dicke und somit mit geringerem Gewicht der daraus hergestellten Strahlenschutzkleidung erreicht wird. Weiter versteht es sich von selbst, dass neben Gadolinium auch andere Zusätze mit großem Neutronen-Absorptionsquerschnitt - beispielsweise Bor oder Bor-Verbindungen - zum Einsatz kommen können. Bei
der Auswahl solcher Zusätze ist zu berücksichtigen, wie diese Zusätze von dem Matrixmaterial aufgenommen und in diese eingemischt werden können, wobei die Benetzbarkeit dieser Zusätze durch das Matrixate- rial zu beachten ist.The measured values in the diagnostically interesting range below 120 kV are significantly larger than the additive values, so that the desired radiation attenuation is achieved with a smaller thickness and thus with a lower weight of the radiation protection clothing made from it. It goes without saying that, in addition to gadolinium, other additives with a large neutron absorption cross section - for example boron or boron compounds - can also be used. at The selection of such additives must take into account how these additives can be taken up by the matrix material and mixed into them, whereby the wettability of these additives by the matrix material must be taken into account.
Diese aus einem Strahlenschutzmaterial auf Basis einer Elastomer-Matrix hergestellte Folie eignet sich zur Herstellung eines Materials für Strahlenschutzkleidungen, wie beispielsweise Schürzen. Dabei werden neben einem einlagigen Material auch mehrlagige Materialien eingesetzt, wobei auch gleiche Folien in mehreren Lagen verwendet werden. Der gegenüber einfacher Addition der einzelnen Schwächungsgleichwerte höhere Schwächungsgleichwerte der Kombination erlaubt dabei eine Verringerung der Dicke des Materials für die Strahlenschutzkleidung und damit auch deren Fl chengewicht.
This film, which is made from a radiation protection material based on an elastomer matrix, is suitable for producing a material for radiation protection clothing, such as aprons. In addition to a single-layer material, multi-layer materials are also used, the same foils being used in several layers. The higher attenuation equivalents of the combination, which are higher than the simple addition of the individual attenuation equivalents, allow a reduction in the thickness of the material for the radiation protective clothing and thus also its surface weight.
Claims
1. Bleifreies Strahlenschutzmaterial aus einem Elastomer oder einem Plastomer als Matrixmaterial in das als Strahlungsabsorbierende Materialien Elemente mit einer Ordnungszahl größer 50 oder deren Verbindungen eingearbeitet sind, dadurch gekennzeichnet, dass als strahlungsabsor- bierende Materialien eine Kombination von Antimon und Bismuth vorgesehen ist.1. Lead-free radiation protection material made of an elastomer or a plastomer as a matrix material into which elements with an atomic number greater than 50 or their compounds are incorporated as radiation-absorbing materials, characterized in that a combination of antimony and bismuth is provided as the radiation-absorbing materials.
2. Strahlenschutzmaterial nach Anspruch 1, dadurch gekennzeichnet, dass als weiterer Zusatz Wolfram oder Wolfram-Verbindungen vorgesehen ist/sind.2. Radiation protection material according to claim 1, characterized in that tungsten or tungsten compounds are / are provided as a further additive.
3. Strahlenschutzmaterial nach Anspruch 2, dadurch gekennzeichnet, dass der Zusatz von Verbindungen des Wolframs in Form von Wolfra at, vorzugsweise als Erdalkali -Wolframat vorgesehen ist.3. Radiation protection material according to claim 2, characterized in that the addition of compounds of tungsten in the form of wolfra at, preferably as alkaline earth tungstate is provided.
4. Strahlenschutzmaterial nach einem der Ansprüche 1 bis 3, dadurch gekennzeichnet, dass als weiterer Zusatz Elemente oder deren Verbindungen aus der Gruppe der seltenen Erden, vorzugsweise Gadolinium oder Cer vorgesehen sind.4. Radiation protection material according to one of claims 1 to 3, characterized in that elements or their compounds from the group of rare earths, preferably gadolinium or cerium, are provided as a further additive.
5. Strahlenschutzmaterial nach Anspruch 4, dadurch gekennzeichnet, dass der Zusatz von Verbindungen seltener Erden, vorzugsweise von Gadolinium oder Cer, in Form von Oxiden oder Carbonaten vorgesehen ist.5. Radiation protection material according to claim 4, characterized in that the addition of rare earth compounds, preferably gadolinium or cerium, is provided in the form of oxides or carbonates.
6. Strahlenschutzmaterial nach einem der vorstehenden Ansprüche 1 bis 5 für einen Schwächungsgleichwert für Röntgenstrahlungsenergien im Bereich von 60 kV bis 125 kV von mindestens 0,135 mm Pb bei einem Nenn- Bleigleichwert von 0,125 mm, gekennzeichnet durch folgende Zusammensetzung: Matrixmaterial: 16 Gew& bis 18 Gew&, Antimon Sb: 25 Gew% bis 35 Gewft. Bismuth Bi: 30 Gew£ bis 40 Gewft, Gadolinium Gd: 8 Gew% bis 14 Gew£, Wolfram W: 5 Gevι% bis 9 Gewft und Cer Ce: 3 Gew% bis 7 Gew£.6. Radiation protection material according to one of the preceding claims 1 to 5 for an attenuation equivalent for X-ray energies in the range from 60 kV to 125 kV of at least 0.135 mm Pb with a nominal lead equivalent of 0.125 mm, characterized by the following composition: Matrix material: 16% by weight to 18% by weight, antimony Sb: 25% by weight to 35% by weight. Bismuth Bi: 30 wt. To 40 wt., Gadolinium Gd: 8 wt.% To 14 wt., Wolfram W: 5 wt.% To 9 wt. And Cer Ce: 3 wt.% To 7 wt.
7. Strahlenschutzmaterial nach Anspruch 6, gekennzeichnet durch folgende Zusammensetzung: Matrixmaterial: 18 Gew£, Antimon Sb: 30 Gevι%. Bismuth Bi: 35 Gew&, Gadolinium Gd: 11 Gevι%, Wolfram W: 7 Gew£ und Cer Ce: 5 Gew£.7. Radiation protection material according to claim 6, characterized by the following composition: matrix material: 18 pounds, antimony Sb: 30% by weight. Bismuth Bi: 35 Gew &, Gadolinium Gd: 11 Gevι%, Wolfram W: 7 Gew £ and Cer Ce: 5 Gew £.
8. Verwendung des Strahlenschutzmaterials nach einem der vorgehenden Ansprüche 1 bis 7, dadurch gekennzeichnet, dass mindestens eine Einzelfolie für die Strahlenschutzkleidungen vorgesehen ist.8. Use of the radiation protection material according to one of the preceding claims 1 to 7, characterized in that at least one individual film is provided for the radiation protection clothing.
9. Verwendung des Strahlenschutzmaterials nach Anspruch 6, dadurch gekennzeichnet, dass zwei oder drei Einzelfolien für die Strahlenschutzkleidungen vorgesehen sind, die zumindest an den umlaufenden Rändern zusammenge- fasst sind. 9. Use of the radiation protection material according to claim 6, characterized in that two or three individual foils are provided for the radiation protection clothing, which are combined at least on the circumferential edges.
Applications Claiming Priority (2)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| DE102004002500 | 2004-01-17 | ||
| DE102004002500.2 | 2004-01-17 |
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| WO2005068544A2 true WO2005068544A2 (en) | 2005-07-28 |
| WO2005068544A3 WO2005068544A3 (en) | 2009-02-05 |
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| PCT/EP2005/050156 WO2005068544A2 (en) | 2004-01-17 | 2005-01-14 | Radiation protection material |
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Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| WO2013040666A1 (en) * | 2011-09-23 | 2013-03-28 | Planideia Confecção De Vestuário De Proteção Ltda. - Epp | Radiopaque carbon-carbon linked elastomeric materials, preparation method and uses of same |
| CN113929356A (en) * | 2021-11-19 | 2022-01-14 | 中纺院（浙江）技术研究院有限公司 | Flexible lead-free X-ray protection material and preparation method and application thereof |
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| EP0371699A1 (en) * | 1988-11-25 | 1990-06-06 | Du Pont Canada Inc. | Radiation protection material |
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2005
- 2005-01-14 WO PCT/EP2005/050156 patent/WO2005068544A2/en active Application Filing
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Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| WO2013040666A1 (en) * | 2011-09-23 | 2013-03-28 | Planideia Confecção De Vestuário De Proteção Ltda. - Epp | Radiopaque carbon-carbon linked elastomeric materials, preparation method and uses of same |
| CN113929356A (en) * | 2021-11-19 | 2022-01-14 | 中纺院（浙江）技术研究院有限公司 | Flexible lead-free X-ray protection material and preparation method and application thereof |
| CN113929356B (en) * | 2021-11-19 | 2022-10-28 | 中纺院（浙江）技术研究院有限公司 | Flexible lead-free X-ray protection material and preparation method and application thereof |
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| Publication number | Publication date |
|---|---|
| WO2005068544A3 (en) | 2009-02-05 |
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