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
  • G21F1/10—Organic substances; Dispersions in organic carriers
  • G21F1/103—Dispersions in organic carriers
  • G21F1/106—Dispersions in organic carriers metallic dispersions

Definitions

• This invention relates to a radiation shielding material for simultaneously shielding gamma-rays, X-rays and neutron rays. More particularly, it relates to a radiation shielding material for radiation facilities, for containers for storing and transporting radioactive wastes, nuclear fuels, radioisotope (RI) and the like, and for associated apparatuses and appliances.
• RI radioisotope
• any materials do not make a great difference therebetween in a mass attenuation coefficient, and because a material having a high density has a large linear attenuation coefficient and it can be used in a less thickness as a shielding body, lead, iron, concrete, etc., have been generally used as shielding materials.
• a material such as polyethylene, paraffin or water for shielding neutron rays, and a material such as lead or iron for shielding gamma-rays have heretofore been used in combination by laminating these two kinds of materials.
• radiation facilities, containers for storing and transporting radioactive wastes, nuclear fuels, RIs and the like, and associated apparatuses and appliances, which are particularly accompanied with the emission of neutron rays are constructed or fabricated from concrete, lead or iron each having a high density, and, furthermore, a shielding body is prepared from polyethylene, paraffin or water which is quite different as a shielding material from the above concrete etc., or a concrete structure alone is used as the shielding body.
• the wall thickness must be considerably great because the shielding capacity of concrete is not sufficiently high, thereby to make the available area of the facility small. Further, the concrete structure is likely to absorb radioactively contaminated water due to its water absorptivity, and, therefore, a water-proofing coating or top coat of a polymer concrete must be formed on the concrete structure. This results in a drastic increase of shielding cost.
• the hydrogen content (wt.%) of a composition comprising a high density inorganic material and a synthetic resin remarkably decreases as compared with that of a molded article made of such a resin alone as used as the matrix in said composition, and the neutron shielding capacity of the composition decreases accordingly.
• the present inventors have paid their close attention to the fact that what is important for shielding neutron rays is not a mere hydrogen content (wt.%) but the number of hydrogen atoms per unit volume (hydrogen atom density) of a shield used, and have found out that a composition obtained by mixing a high-density inorganic material with a thermosetting resin material containing a large quantity of hydrogen does not exhibit a remarkable decrease in hydrogen atom density as compared with such a resin alone as used as the matrix in said composition, and has performance rather superior to the matrix resin alone in respect of the shielding effect on neutron rays.
• the present invention has been made on the basis of this finding.
• a radiation shielding material capable of simultaneously shielding gamma- and X-rays, and neutron rays, which comprises 50 to 2,000 parts by weight of at least one inorganic material selected from the group consisting of Pb, W, Cr, Co, Cu, Fe, Mn, Mo, Ag, Ta, Cd, Dy, Eu, Gd, Au, In, Hg, Re, Sm, U and compounds thereof, based on 100 parts by weight of at least one thermosetting resin material selected from the group consisting of a phenol resin, an epoxy resin, a cresol resin, a xylene resin, a urea resin and an unsaturated polyester, and wherein the density of a molded article of said inorganic material-containing resin is at least 2.0.
• thermosetting resin which contains a large quantity of hydrogen and is highly resistant to heat, is a preferable one for use in the radiation shielding material according to the present invention.
• the thermosetting resins which may be used in the present invention include a phenol resin, an epoxy resin, a cresol resin, a xylene resin, an urea resin, an unsaturated polyester and the like. These thermosetting resins may be used singly or jointly by mixing these resins.
• the thermosetting resin has a sufficient strength, excellent moldability and machinability, and has a relatively high heat resistance. Depending on the resin selected, it can be used at temperatures above 150 °C.
• the range of the molecular weight of the thermosetting resin used in the present invention and the degree of polymerization thereof are not particularly limited.
• an inorganic material having a high density and containing a large amount of such an element or a combination of such materials can be used to produce a radiation shielding material having a further higher effect.
• the high-density inorganic material to be used for the present invention is at least one member selected from the group consisting of Pb, W, Cr, Co, Cu, Fe, Mn, Mo, Ag, Ta, Cd, Dy, Eu, Gd, Au, In, Hg, Re, Sn and U alone and compounds thereof, in the form of powder or pellet.
• These compounds include minerals such as iron ore, nickel ore and copper ore.
• the amount of the inorganic materials added to the thermosetting resin is preferably within the range of from 50 to 2,000 parts by weight based on 100 parts by weight of the thermosetting resin. If the amount is less than 50 parts by weight, the shielding effect on gamma-rays and X-rays is inferior, and if it exceeds 2,000 parts by weight, the shielding effect on neutron rays decreases and at the same time, molded articles obtained are brittle and their mechanical strength decreases.
• the highest shielding effect can be obtained by suitably determining a mixing ratio within the above mixing range depending on the intensity and characteristics of each radiation to effect shielding in the environment where various radiations such as neutron rays and gamma-rays co-exist.
• the resulting molded article When the above mixture or composition is cured and molded, the resulting molded article must have a density of at least 2.0. If it has a density of less than 2.0, its shielding effect on gamma- and X-rays is inferior whereby simultaneous shielding of these different rays is made impossible. Since the density of concrete is generally from 2.0 to 2.2, the density of the molded article must be greater than the shielding capacity of concrete.
• thermosetting resin is mixed with the high-density inorganic material and further with a hydrogen-occluding alloy which has a relatively high dissociation temperature and can hold hydrogen therein up to a high temperature, thereby to further increase the resulting mixture in hydrogen atom density while allowing it to keep its high density.
• the hydrogen-occluding alloy is very effective for simultaneously shielding neutron rays, gamma-rays and X-rays, because it has a hydrogen atom density equally to polymer compounds such as the resin but has a higher density than the polymer compounds.
• the hydrogen-occluding alloy can store hydrogen in the form of a metal hydride by reacting it with hydrogen gas.
• the hydrogen-occluding alloys such as Ti type, La (R) type, Mg type and Ca type ones are known, among which the Mg-type alloy which has a high hydrogen dissociation temperature at a normal pressure is believed to be the most suitable for the object of the present invention.
• the hydrogen-occluding alloys that can be used in the present invention include metal hydrides of Mg origin such as MgH2, Mg-Ni origin such as Mg2NiH 4.2 , Mg-Cu origin such as MgCuH 2.7 , Mg-Ca origin such as MgCaH 3.72 and La-Mg origin such as La2Mg17H17.
• the amount of hydrogen-occluding alloy added is preferably within the range of from 1 to 50 parts by weight based on 100 parts by weight of the thermosetting resin, in view of the cost of the resulting product and radiation shielding performance thereof.
• the test for shielding performance was conducted by determining the thickness (1/10 value layer) of each test piece which reduces the dose equivalent rate of each radiation to 1/10, and making evaluation by using the 1/10 value layer.
• the test used 252Cf as the neutron source and 60Co as the gamma-ray source.
• test pieces of Nos. 2 to 9 which are Examples have neutron shielding capability equal to, or higher than, that of the epoxy resin alone of No. 1 which is Comparative Example, have improved gamma-ray shielding capability due to the increase of their densities, and also have high performances of shielding gamma-rays and X-rays as well as neutron rays.
• test pieces of Nos. 10, 11 and 13 which are Examples have neutron-ray shielding capacity equal to, or higher than, that of concrete of No. 16 as a Comparative Example, have excellent gamma-ray shielding capability approximate to that of the carbon steel (SS41) of No. 17, and have high gamma- and X-ray shielding performances and neutron-ray shielding performance.
• test pieces each having the same composition as that of No. 7 in Test 1, one being prepared without addition of a defoaming or anti-foaming agent thereto, another without degassing-kneading treatments and still another without any of such addition and treatments.
• These test pieces so prepared were each tested for density and shielding performance in comparison with the test piece of No. 7.
• the defoaming agent was a silicone-based one which was added to a mixture of the resin and inorganic materials in an amount of 1 wt.% of the mixture, and the degassing-kneading was carried out at a reduced pressure.
• Table 2 The test results are as shown in Table 2.
• the procedure for preparing the test piece of No. 5 was followed except that the Wolframite was reduced in amount and, instead, a hydrogen-occluding Mg-Ni alloy (Mg2NiH 4.2 ) was used as one of the component materials, thereby to obtain a new test piece (No. 21) comparison.
• the procedure for preparing the test piece of No. 6 was followed except the lead oxide was reduced in amount and, instead, the same Mg-Ni alloy as above was used as one of the component materials, thereby to obtain a new test piece (No. 22).
• These new test pieces so obtained were each tested for density, hydrogen atom density and shielding performance, in comparison with those of No. 5 and 6, respectively.
• the Mg-Ni type hydrogen-occluding alloy can hold hydrogen up to a high temperature of 300 °C or above under a normal state.
• the component materials for the test pieces Nos. 21 and 22 were also subjected to degassing-kneading and incorporated with the foaming agent. The results are shown in Table 3.
• test pieces of Nos. 21 and 22 obtained by including the hydrogen-occluding alloy as one of the component materials as mentioned above have gamma-ray shielding performances equivalent to those of the test pieces of Nos. 5 and 6 not containing the hydrogen-occluding alloy, respectively, but they have higher neutron-ray shielding performances than those of the test pieces of Nos. 5 and 6, respectively. Therefore, it is apparent that the former are superior to the latter.
• the radiation shielding materials according to the present invention have far higher simultaneous shielding capability against gamma-rays, X-rays and neutron rays than conventional laminate type materials and concrete, the former can be made compact in size.
• the optimum shielding material can be designed by appropriately changing the mixing ratio of the component or raw materials.
• a shielding material having mechanical strength and heat resistance sufficient for use can be produced by selecting the kinds of thermosetting resin and high-density inorganic materials and the production method for the shielding material.
• Technology for molding the thermosetting resin as the matrix has been already established in various fields, and the shielding materials of the present invention can be produced by utilizing such technology and equipment. Accordingly, and, thus, it is possible to stably provide the shielding materials at a lower cost.

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• Chemical & Material Sciences (AREA)
• Dispersion Chemistry (AREA)
• Physics & Mathematics (AREA)
• Engineering & Computer Science (AREA)
• General Engineering & Computer Science (AREA)
• High Energy & Nuclear Physics (AREA)
• Compositions Of Macromolecular Compounds (AREA)
• Paints Or Removers (AREA)

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• 1992
  • 1992-12-11 JP JP4352400A patent/JPH06180389A/ja active Pending
• 1993
  • 1993-12-10 EP EP94902107A patent/EP0628968A4/de not_active Withdrawn
  • 1993-12-10 WO PCT/JP1993/001799 patent/WO1994014167A1/ja not_active Application Discontinuation

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