EP1460641B1 - Dispositif de protection contre les radiations - Google Patents

Dispositif de protection contre les radiations Download PDF

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Publication number
EP1460641B1
EP1460641B1 EP04006054A EP04006054A EP1460641B1 EP 1460641 B1 EP1460641 B1 EP 1460641B1 EP 04006054 A EP04006054 A EP 04006054A EP 04006054 A EP04006054 A EP 04006054A EP 1460641 B1 EP1460641 B1 EP 1460641B1
Authority
EP
European Patent Office
Prior art keywords
radiation
gypsum
radiation shielding
arrangement according
shielding 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 - Lifetime
Application number
EP04006054A
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German (de)
English (en)
Other versions
EP1460641A1 (fr
Inventor
Willi Brüchle
Georg Fehrtenbacher
Torsten Radon
Frank Gutermuth
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.)
GSI Helmholtzzentrum fuer Schwerionenforschung GmbH
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GSI Helmholtzzentrum fuer Schwerionenforschung 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.)
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Publication date
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Publication of EP1460641A1 publication Critical patent/EP1460641A1/fr
Application granted granted Critical
Publication of EP1460641B1 publication Critical patent/EP1460641B1/fr
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Expired - Lifetime legal-status Critical Current

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Classifications

    • 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
    • G21F1/04—Concretes; Other hydraulic hardening materials
    • 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

Definitions

  • the invention relates generally to a radiation shielding arrangement and to a radiation shielding arrangement for shielding neutron radiation and gamma radiation from particle accelerators or storage rings, in particular for synchrotron radiation sources in particular.
  • HERA has a scope of 6.3 km, so that cost savings are of particular interest.
  • the EP 0 585 184 A1 relates to a building material for shielding electromagnetic radiation containing, for example Portland cement or gypsum.
  • the gypsum only serves as a building material and has no radiation-shielding function.
  • the manufactured plate is provided as a shield against electrosmog and not suitable for high-energy gamma radiation and / or fast neutrons.
  • the JP 11202090 describes a neutron shielding body with combustion ash.
  • the gypsum is only used as a binder and not as a shielding material.
  • the U.S. Patent 3,705,101 describes a neutron absorber with gypsum as a hydrogen source for moderating neutrons.
  • the material is intended for a container for transporting nuclear fuel and does not seem to be suitable for shielding particle accelerators.
  • the RU 19950119981 describes a radiation shield in which gypsum wastes are used. A plate only 150 mm thick is described for the shielding of beta and gamma radiation. This does not appear to be suitable for shielding neutrons from accelerator systems.
  • the DE 36 07 190 A1 relates to a gypsum radiation protection plate. However, this is based on a conventional drywall of only 12.5 mm thickness, wherein the gypsum barium is added as an absorber for X-rays.
  • the plate is neither suitable for shielding gamma radiation nor neutrons, in particular not for particle accelerators and the energies occurring. Furthermore, the plate is also not suitable for the absorption or moderation of high-energy neutrons.
  • the GB 1 200 926 relates to radiation shielding for gamma rays and neutrons for which dysprosium and carbon are used as moderators and gadolinium as absorber after the thermalization of the neutrons. This material is only designed to shield spacecraft and rockets. Gypsum is not mentioned as a hydrogen supplier for moderating fast neutrons nor is it suitable for shielding high-energy accelerators.
  • the WO 96/36972 relates to a method for producing shielding elements.
  • the shielding elements are apparently intended for immersion in a sinking basin.
  • an electrolytic coating with cadmium of a thickness of only up to 300 ⁇ is proposed.
  • these shielding elements are neither intended nor suitable for shielding particle accelerators.
  • the U.S. Patent 3,995,163 describes a device for neutron therapy in which neutrons with the characteristic energy up to 14 MeV are generated during tritium decay. Thus, the neutron energies are orders of magnitude lower than at High-energy accelerators. Further, no gypsum is used, but metals such as iron, nickel or copper are used to decelerate the neutrons. Again, this does not seem to be suitable for high energy particle accelerators or storage rings.
  • Yet another object of the invention is to provide a radiation shielding arrangement for shielding neutron radiation and gamma radiation from particle accelerators or storage rings which has low activation even at high gamma and neutron energies.
  • Another object is to provide a radiation shielding arrangement for shielding neutron radiation and gamma radiation from particle accelerators or storage rings which avoids or at least mitigates the disadvantages of the prior art.
  • the radiation shielding arrangement according to the invention comprises a shielding element of hydrous material, e.g. with chemically bound water, especially water of crystallization.
  • the water content of the material is at least 5, 10 or 20 percent by weight.
  • the shielding element is at least 75 weight percent, at least 90 weight percent or im essentially entirely of plaster.
  • gypsum in particular a gypsum wall consisting essentially of set or hardened gypsum, chemically CaSO 4 .2H 2 O, has proven to be particularly suitable since the calcium absorbs gamma radiation relatively effectively due to its nuclear charge of 20.
  • the bound water of crystallization about 20% by weight relative to the total weight of the gypsum, in turn provides the protons.
  • the thickness of the shielding element is particularly related to the radiation spectra of a high energy particle accelerator and / or high energy particle storage ring for electrons, positrons or ions, e.g. a synchrotron, especially adapted for particle energies of greater than 10 GeV or greater than 30 GeV.
  • neutron absorber layer of a material which absorbs the moderated neutrons.
  • Boron, boron-paraffin, cadmium and / or gadolinium have proved particularly suitable for this purpose.
  • a multilayer arrangement, in particular the attachment of a separate neutron absorber layer on the plaster wall is particularly advantageous in this regard, since the stability of the gypsum is maintained.
  • no boron or other neutron absorbing material has to be mixed into the gypsum.
  • the assembly may be modular, e.g. block formed.
  • one-sided or two-sided support layers or cladding e.g. to provide concrete, which cause a double benefit, namely a stabilization and an additional shield against gamma radiation.
  • the concrete formwork can provide the necessary stability, so that radiation shielding arrangements can be used whose gypsum wall alone would not be self-supporting, but then self-supporting in connection with the shuttering, i. the radiation shielding arrangement has self-supporting stability properties due to the base layer or base layers. The thickness of the base layer will be especially dimensioned accordingly.
  • a neutron absorber layer containing a neutron absorbing material is provided. This is mounted on the side facing away from the accelerator, in particular directly on the shielding element.
  • the neutron absorber layer contains e.g. Boron, boron-containing glass or boron paraffin.
  • the neutron absorber layer is preferably arranged within the casing and / or between the casing and the wall made of gypsum.
  • the casing in particular the concrete casing, itself contains a neutron-absorbing material, e.g. a boron-containing material.
  • a neutron-absorbing material e.g. a boron-containing material.
  • It can e.g. Boric acid or boron carbide the casing material, e.g. be mixed with the concrete.
  • the casing has boron-containing glass. This is significantly less expensive than boron carbide and, even when blended, preserves the stability of the concrete better than boric acid.
  • Boron-containing glass may in particular be used instead of or in addition to commonly used additives such as e.g. Gravel are added.
  • the material of the shielding element in particular the gypsum, may also contain boron-containing glass.
  • REA gypsum flue gas desulphurisation plants
  • This is deposited at millions of tons expensive dumps. Every year more than 3 million tonnes of REA gypsum are produced in Germany. Therefore, the electricity providers may even be ashamed if they can deliver the material.
  • the REA gypsum is chemically very pure, thereby diminishing long-lived radiant activity from high atomic number elements. Therefore, REA gypsum is also more suitable as concrete from the point of view of activation.
  • shielding or gypsum walls of about 1 m to 10 m, preferably 2 m to 8 m, more preferably 4 m to 7 m thickness will be required.
  • the quantity of gypsum should therefore be at least 100,000 tonnes or even a multiple thereof.
  • the radiation shielding arrangement according to the invention is thus prepared, in particular with regard to the shielding effect or the thickness of the shielding element, to shield neutron radiation and gamma radiation from high energy particle accelerators, storage rings, target, experimental and / or analytical devices, in particular at particle energies greater than 1 GeV or even greater than 10 GeV.
  • FIG. 1 Figure 4 shows the simulation results of penetrating dose or residual radiation dose through a shielding element or screen in Pico-Sievert (pSv) per proton as a function of shielding or wall thickness in centimeters (cm).
  • pSv Pico-Sievert
  • the results are broken down by neutron dose and dose of electromagnetic radiation (gamma dose) as well as the total dose each for gypsum and concrete.
  • the shielding effect is more than a factor of two higher than for concrete and the total dose shielding is about 20% to 25% better for gypsum than for concrete.
  • the maximum of the curves represents the secondary radiation equilibrium, from which an attenuation effect occurs.
  • the secondary radiation equilibrium thickness is approximately between 60 cm and 70 cm.
  • Table 1 shows values for the generation of radioactivity during a 30-year blasting operation and a subsequent cooldown of 5 years for concrete and gypsum.
  • the radionuclides listed in Table 1 are mainly produced, namely H-3, Na-22, Mn-54 and Fe-55.
  • the values for the activity are normalized to the total activity of gypsum.
  • gypsum produces a radioactivity which is lower by a factor of about 1.2. Furthermore, the type of radioactivity generated, i. the distribution of the radionuclides produced in gypsum more favorably than in concrete, if one takes the release values according to the current radiation protection law as a yardstick (factor 4.41). It follows that the costs for a subsequent disposal after the end of the use of the radiation shielding arrangement according to the invention will be lower than in conventional shields.
  • FIG. 2 shows a multilayer radiation shielding assembly 10 having one, the radiation source and the particle beam 20 facing first layer or spallation layer 11 consisting of or containing a metal, in particular with a core mass> 50 atomic mass units (amu), eg iron.
  • a first shielding element a wall or a first shielding layer 12 consisting of or containing a material for decelerating neutrons, eg plaster and / or concrete, is arranged.
  • a neutron absorber layer 13 consisting of or containing a material which is suitable for absorbing thermalized neutrons, for example boron, cadmium or gadolinium.
  • a second shielding layer 14 which is of a smaller thickness than the wall 12, consisting of or containing a material for decelerating neutrons, such as plaster and / or concrete arranged.
  • the iron induced by the high-energy neutrons 21, causes spallation reactions, which in turn release neutrons 22 with lower energy. This achieves an indirect first moderation.
  • spallation neutrons 22 are further decelerated in the wall 12, to be finally captured and absorbed by the atomic nuclei of the neutron absorbing layer 13.
  • the material for the spallation layer 11 can also come from the disposal of materials from nuclear facilities, where weakly activated metals are produced in larger quantities.

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  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Particle Accelerators (AREA)
  • Laminated Bodies (AREA)
  • Packages (AREA)
  • Analysing Materials By The Use Of Radiation (AREA)
  • Radiation-Therapy Devices (AREA)
  • Shielding Devices Or Components To Electric Or Magnetic Fields (AREA)

Claims (17)

  1. Agencement de protection contre le rayonnement pour la protection contre le rayonnement neutronique et/ou le rayonnement gamma d'accélérateurs de particules, d'anneaux de stockage de particules, de dispositifs cibles, d'expérimentation ou d'analyse, comprenant
    une couche de spallation (11), dans laquelle des neutrons (22) sont libérés dans des réactions de spallation et
    au moins un élément de blindage à base d'un premier matériau contenant du plâtre, afin de freiner les neutrons de spallation (22).
  2. Agencement de protection contre le rayonnement selon la revendication 1,
    caractérisé en ce que
    le premier matériau contient le plâtre dans l'état pris dans la composition chimique CaSO4*2H2O.
  3. Agencement de protection contre le rayonnement selon l'une quelconque des revendications précédentes, caractérisé en ce que l'élément de blindage comprend un mur en plâtre.
  4. Agencement de protection contre le rayonnement selon l'une quelconque des revendications précédentes, caractérisé en ce que le mur en plâtre présente une épaisseur qui est adaptée aux spectres de rayonnement d'un accélérateur de particules à haute énergie et/ou d'un anneau de stockage de particules à haute énergie pour des électrons, des positrons ou des ions.
  5. Agencement de protection contre le rayonnement selon l'une quelconque des revendications précédentes, caractérisé en ce que le mur présente une épaisseur qui est supérieure ou égale à l'épaisseur d'équilibre du rayonnement secondaire, en particulier une épaisseur d'au moins 2 m, d'au moins 5 m ou d'au moins 7 m.
  6. Agencement de protection contre le rayonnement selon l'une quelconque des revendications précédentes, caractérisé par une structure à plusieurs couches.
  7. Agencement de protection contre le rayonnement selon l'une quelconque des revendications précédentes, caractérisé par une structure modulaire.
  8. Agencement de protection contre le rayonnement selon l'une quelconque des revendications précédentes, caractérisé par une couche portante, qui est disposée sur un premier côté de l'élément de blindage et la couche portante présente au moins une épaisseur minimale qui est dimensionnée de telle sorte que l'agencement de protection contre le rayonnement est en particulier l'agencement à base d'élément de blindage et de couche portante.
  9. Agencement de protection contre le rayonnement selon la revendication 8,
    caractérisé en ce que
    la couche portante est un coffrage en béton.
  10. Agencement de protection contre le rayonnement selon l'une quelconque des revendications précédentes, caractérisé en ce que l'élément de blindage est doté d'un coffrage sur les deux côtés, en particulier en béton.
  11. Agencement de protection contre le rayonnement selon l'une quelconque des revendications précédentes, caractérisé par une couche d'absorption de neutrons, qui contient un matériau absorbant les neutrons.
  12. Agencement de protection contre le rayonnement selon l'une quelconque des revendications précédentes, caractérisé par une couche d'absorption de neutrons, qui contient du bore, du cadmium et/ou du gadolinium.
  13. Agencement de protection contre le rayonnement selon l'une quelconque des revendications précédentes, caractérisé par une couche d'absorption de neutrons, qui contient du bore et de la paraffine.
  14. Agencement de protection contre le rayonnement selon l'une quelconque des revendications précédentes,
    caractérisé en ce que la couche d'absorption de neutrons est disposée à l'intérieur du coffrage et/ou entre le coffrage et le mur en plâtre.
  15. Agencement de protection contre le rayonnement selon la revendication 8,
    caractérisé en ce que
    la couche portante comprend un matériau d'absorption de neutrons.
  16. Agencement de protection contre le rayonnement selon l'une quelconque des revendications précédentes,
    la couche de spallation contenant un métal.
  17. Utilisation de plâtre REA provenant d'installations de désulfuration des gaz de fumée pour la fabrication d'un agencement de protection contre le rayonnement, le plâtre REA étant utilisé comme matériau de blindage pour la protection contre le rayonnement neutronique et/ou le rayonnement gamma d'accélérateurs de particules à haute énergie, d'anneaux de stockage de particules à haute énergie, de dispositifs cibles, d'expérimentation ou d'analyse,
    le plâtre REA étant utilisé sous la forme d'un mur (12) à base de plâtre REA pris,
    l'eau de cristallisation liée dans le plâtre REA mettant à disposition les atomes d'hydrogène pour la modération des neutrons et
    le mur en plâtre REA (12) présentant une épaisseur qui est supérieure ou égale à l'épaisseur d'équilibre du rayonnement secondaire.
EP04006054A 2003-03-19 2004-03-15 Dispositif de protection contre les radiations Expired - Lifetime EP1460641B1 (fr)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
DE10312271A DE10312271A1 (de) 2003-03-19 2003-03-19 Strahlungsabschirmungsanordnung
DE10312271 2003-03-19

Publications (2)

Publication Number Publication Date
EP1460641A1 EP1460641A1 (fr) 2004-09-22
EP1460641B1 true EP1460641B1 (fr) 2009-12-30

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EP04006054A Expired - Lifetime EP1460641B1 (fr) 2003-03-19 2004-03-15 Dispositif de protection contre les radiations

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US (1) US6927407B2 (fr)
EP (1) EP1460641B1 (fr)
AT (1) ATE453915T1 (fr)
DE (2) DE10312271A1 (fr)

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DE102004063732B4 (de) * 2004-12-29 2013-03-28 Gsi Helmholtzzentrum Für Schwerionenforschung Gmbh Strahlenschutzkammer mit insbesondere einer mehrschichtigen Strahlenschutzwand
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JP6322359B2 (ja) * 2012-10-30 2018-05-09 株式会社竹中工務店 放射線遮蔽壁、放射線遮蔽壁の施工方法及び放射線遮蔽壁の修復方法
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CN108053906B (zh) * 2017-12-14 2019-08-06 东莞理工学院 一种用于中子科学研究的防辐射块及其制备方法
CN108010596A (zh) * 2018-01-19 2018-05-08 中国科学院合肥物质科学研究院 一种适用于强核辐照环境的抗辐射屏蔽装置
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CN110372286A (zh) * 2019-06-21 2019-10-25 东南大学 一种核泄漏防护复合墙体及其应用
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Publication number Publication date
DE10312271A1 (de) 2004-10-07
DE502004010569D1 (de) 2010-02-11
ATE453915T1 (de) 2010-01-15
US6927407B2 (en) 2005-08-09
US20040217307A1 (en) 2004-11-04
EP1460641A1 (fr) 2004-09-22

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