US2961415A - Settable neutron radiation shielding material - Google Patents

Settable neutron radiation shielding material Download PDF

Info

Publication number
US2961415A
US2961415A US620147A US62014756A US2961415A US 2961415 A US2961415 A US 2961415A US 620147 A US620147 A US 620147A US 62014756 A US62014756 A US 62014756A US 2961415 A US2961415 A US 2961415A
Authority
US
United States
Prior art keywords
composition
settable
neutrons
boron
polyethylene
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
US620147A
Other languages
English (en)
Inventor
Irving R Axelrad
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.)
Individual
Original Assignee
Individual
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.)
Filing date
Publication date
Priority to BE567962D priority Critical patent/BE567962A/xx
Application filed by Individual filed Critical Individual
Priority to US620147A priority patent/US2961415A/en
Application granted granted Critical
Publication of US2961415A publication Critical patent/US2961415A/en
Anticipated expiration legal-status Critical
Expired - Lifetime legal-status Critical Current

Links

Images

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
    • 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
    • G21F1/026—Semi-liquids, gels, pastes

Definitions

  • The, present invention relates to neutron radiation shieldingmaterial and has particular reference to settable compositions adapted for application about radioactive areas to. attenuate fast moving neutrons and capture slowmoving neutrons.
  • v 1
  • Polyethylene is one relatively high hydrogen content material. which has been used to provide a neutron shield about radioactive areas. Also, in some instances boron, or compounds thereof, has-been incorporated in the polyethylene. Heretofore, polyethylene, with or without boron therein, has been used only in sheet or slab form. Such sheets or slabs are not completely suitable for use when it is necessary to shield reactor parts having spherical surfaces, S-bends and other irregular shapes.
  • the object of the present invention is to provide a settable, viscous, putty-like composition adapted for application as by troweling, casting, or the like about irregularly shaped members to provide a shield capable of attenuating fast moving neutrons and capturing slow moving neutrons.
  • Another object of the present invention is to provide a solid resinous composition adapted for mounting about members enclosing a radioactive area, which composition 'will'attenuate-fast moving neutrons and capture slow moving-neutrons; p
  • Still another object of the'present invention is to provide a settable, viscous, putty-like resinous composition moving neutrons Zflfiififi I Patented Nov. 22, 1960 2 which comprises a material having a high ratio of hydrogen atoms to all other atoms in the resin in intimate combination with boron or a compound thereof in a suitable carrier.
  • Yet another object of this invention is to provide a viscous, putty-like resinous composition which is settable to a solid and which comprises a resinous carrier intimately associated with boron or a compound thereof and a material having a high ratio of hydrogen atoms to all other atoms in the material.
  • Still another object of the present invention is to provide a process for applying a pasty, putty-like composition to a member enclosing a radioactive area, said composition comprising a resinous carrier which is settable to a solid and which is intimately associated with boron or a compound thereof and a material having a high ratio of hydro gen atoms to all other atoms in the material.
  • Figure 1 is. a diagrammatic cross-sectional view of a radioactive area shielded with the composition of this invention.
  • Fig. 2 is a view, partially, in cross-section, of an irregularly shaped structural component, adapted for carrying radioactive material, having a shielding layer composed ofthe composition of this invention.
  • settablemesinous compositions adapted to attenuate fast and capture slow moving neutrons comprising (1) a carrier which is curable to a solid and which is intimately associated with (2) a major proportion of a compound having ahigh ratio of hydrogen atoms to all other atoms in the material in combination with (3) a minor proportion of boronor compounds thereof.
  • the carrier portion of the compositions of this invention is. a fluid resinous material in which the other components of the composition are dissolved, dispersed, suspended, or otherwise distributed.
  • Resinous materials which are suitable for use as carriers in this invention incude liquid or. relatively high viscosity pasty-like castable resins. which cure or set to solids, generally in the presence of a catalyst, hardener, or cure accelerator, eitherat room temperature or at somewhat higher temperatures.
  • resinous materials which are suitable carriers include fluid polyesters, epoxy resins, castable phenol-aldehyde resins, butadiene polymers and copolymers thereof with styrene, and butadieneacrylonitrile copolymers.
  • Such resins include chloroprene polymers and copolymers; vinyl halide and vinylidene halide resins suchas polyvinyl chloride, polyvinylidene bromide, polyfiuorochloroethylene; vinyl chloride and vinylidene chloride copolymers; copolyrners of vinyl halides and vinylidene halides with other unsaturates such'as vinyl chloride with vinyl acetate, vinylidene bromide with vinyl acetate, and ethylene with vinyl chloroa'c'etate; halogenated high molecular weight natural resinsand hydrocarbons such as the commercially available halogenated paraffin waxes, the halogenated natural rubbers, and the like.
  • plasticizers which are suitable for main preparing plastisols in accordance with this invention include di-iso-octyl phthalate, discapryl phthalate, di-noctyl phthalate, butyl benzyl phthalate, di-Z-ethylhexyl phthalate, dibutyl phthalate, dioctyl azelate, dioctyl adipate, dioctyl sebacate, dibenzyl sebacate, tricresyl phosphate, tri-iso-octyl phosphate, octyl diphenyl phosphate, tri-Z-ethylhexyl phosphate, propylene glycol diacetyl ricinoleate, methyl acetyl ricinoleate, tetrahydrofurfuryl oleate and tetraethylene glycol di-isohexoate.
  • the plasticizers may be used sing
  • the plastisols In general, the plastisols must be heated to temperatures in excess of 100 C. to effect a satisfactory cure thereof. Therefore, the plastisols are particularly suitable for use as carriers in the compositions of this invention when it is desired to precast irregularly-shaped shielding sections in the shop and later mount such sections in place about the radioactive area.
  • Other resins such as the castable phenol-aldehyde resins, epoxy resins, and the like, which are curable at room temperature are particularly suitable for use as carriers in the compositions of this invention when it is desired to apply the compositions directly about an irregularly-shaped part, as by troweling, and permit it to harden, set, or cure in place.
  • Boron is incorporated in the compositions of this invention in amounts within the range of about 0.3% to 10% by weight of the total composition and may be employed either as the pure element or in any of its compounds.
  • finely divided amorphous boron, boric acid, boric oxide, and boron carbide have been successfully used in accordance with this invention.
  • Borax also is satisfactory for use in certain circumstances, although care is required to prevent water evolving therefrom when it is incorporated in resinous carriers which require heating to cure them to a solid state.
  • Esters of boron such as glyceryl borate also may be used in the resinous composition.
  • the compound having the high hydrogen atom content which forms an essential component of the composition of this invention may comprise any one or more of those compounds which have a ratio of hydrogen atoms to all other atoms therein within the range of 0.5 :1 to 2:1.
  • the material should be one which will not inhibit the satisfactory cure of the resinous carrier. Moreover, to be completely satisfactory, it must be a material which itself is not adversely affected by the conditions necessary to cure the resinous carrier.
  • the high hydrogen content component of the present compositions may be a solid, a liquid, or have a viscosity anywhere between the extremes of liquids and solids, and it may be soluble in the resinous carrier, prior to the final cure or setting of the carrier, or dispersable, suspendable, or otherwise distributable in the carrier.
  • Examples of materials having a hydrogen atom content within the range specified above which are suitable for use in accordance with this invention include polyethylene, butyl rubber, paraffin, polyisobutylene, and polyisoprene. These materials may be used alone or in mixtures of tWo or more in granular, pellet, fiake, powdered, or other particulate form. They may be employed in the compositions of this invention in amounts within the range of from about 10% to 85%, and preferably about 25% to about 75% by weight based on the total weight of the composition.
  • compositions of this invention it is only necessary to admix the three essential components, viz., (1) the carrier, (2) the high hydrogen content material, and (3) boron, or a compound thereof.
  • these components may be admixed conveniently in a manner similar to the mixing of concrete using a hoe and mortar box.
  • the resinous carrier together with a catalyst, hardener, or cure accelerator therefore is analogous to the water and cement portion of concrete; the high hydrogen content material, in particulate form, and boron or a compound thereof are analogous to the sand-gravel or solid portion of concrete.
  • compositions when thoroughly admixed, have a viscous, putty- 4 like consistency and they either may be poured into suitable forms or applied about surfaces to be shielded by troweling or the like and permitted to harden or set to a solid in place.
  • Example I A fluid-pasty composition was prepared by thoroughly admixing (1) 64 parts of an epoxide resin (Bakelite RR18774), 24 parts of triethylenetetramine, (2) 30 parts of polyethylene (60 mesh), 61 parts of polyethylene /s" granules), and (3) 5 parts of boron carbide.
  • the composition had a polyethylene content of approximately 50.8% by weight. It was introduced into a sheet metal housing member disposed about a pipe adapted for carrying radioactive material. The composition was tamped into the space surrounding said pipe to fill completely all the space therein. The material was found to be suitable in preventing the passage of both fast moving and slow moving neutrons from the radioactive area within the pipe to the surrounding atmosphere.
  • Example II A high hydrogen content composition was prepared by thoroughly admixing 1) 7 lbs. 8 ozs. of a phenolformaldehyde resin (Marblett #71), 11 ozs. of dilute hydrochloric acid, (2) 2 lbs. 6 ozs. of polyethylene (60 mesh) 5 lbs. 7 ozs. of polyethylene cubes), and (3) 1 lb. of boric acid. When troweled about irregular sections of an atomic reactor and cured, this composition was effective in preventing the escape of neutrons from the radioactive area to the outside.
  • a portion of this material was cast into a cake measuring 3 inches x 12 inches x 12 inches and tested for flammability.
  • the test specimen was placed on edge and the flame from an oxygen-natural gas torch (about 5700 F.) was directed on the surface of the block near its center.
  • the tip of the torch was maintained at a distance of approximately one inch from the surface of the block for a period of about two minutes and then removed.
  • the flame produced by the torch extinguished itself in 38 seconds and exhibited no tendency toward spreading.
  • the boric acid in this formulation provided boron atoms useful in the absorption of slow moving thermal neutrons and also increased the resistance of the cast sample to burning.
  • formulations which, when thoroughly admixed, provide viscous, putty-like compositions adapted for casting neutron shields of predetermined shape and compositions adapted for application directly by troweling or the like about structural components in radioactive areas to prevent the escape therefrom of neutrons.
  • Fig. l is a view illustrating in schematic form the use of the composition of this invention.
  • a radioactive area or source 10 is completely surrounded by a metal housing 12 which may be of metal such as steel, stainless steel, aluminum or the like.
  • a primary shielding layer 14 Surrounding the housing 12 there is a primary shielding layer 14. This shield serves to prevent the passage of gamma rays from the radioactive area to the outside.
  • Shield 14 may be constructed of any dense material such as lead, tungsten, or the like. Completely surrounding shield 14 is a secondary shield 16 composed of the composition of this invention. Shield 16 comprises a solid resinous carrier containing a compound having a high hydrogen atom content such as polyethylene, and boron or a compound thereof.
  • FIG. 2 partly in cross-section, illustrates the applicability of the settable compositions of this invention to irregularly-shaped structural components adapted for carrying radioactive material.
  • a stainless steel pipe 18, through which may flow radioactive material, has a bend 20 which cannot be shielded conveniently by the application thereto of slab-s or sheets of shielding material.
  • An eflective neutron radiation shield is provided in accordance with this invention by applying, as by troweling, a quantity of the shielding composition 22 of this invention about the bend 20 in pipe 18.
  • Composition 22 is composed of particles of a compound 24 having a high hydrogen atom content such as polyethylene, boron carbide particles 26, and a cured resinous filler 28.
  • a settable, viscous, putty-like composition consisting essentially of, in combination, an intimate admixture of (a) a major proportion of a compound having a ratio of hydrogen atoms to all other atoms therein within the range of from 0.521 to 2:1 and being selected from at least one of the group consisting of polyethylene, butyl rubber, paraffin, polyisobutylene, and polyisoprene, (b) from 0.5% to 10% by Weight of boron, and (c) a fluid resinous carrier selected from at least one of the group consisting of fluid polyesters, epoxy resins, castable phenol-aldehyde resins, butadiene polymers and copoly- 5 mers thereof with styrene, butadieneacrylonitrile copolymers and plastisols, said composition when cured being adapted to attenuate fast moving neutrons and capture slow moving neutrons.
  • a settable, viscous, putty-like composition adapted to attenuate fast moving neutrons and capture slow moving neutrons consisting essentially of an intimate admixture of from 0.5% to 10% by weight of boron carbide and from 10% to by weight of polyethylene and a fluid resinous carrier selected from at least one of the group consisting of fluid polyesters, epoxy resins, castable phenol-aldehyde resins, butadiene polymers and copolymers thereof with styrene, butadieneacrylonitrile copolymers and plastisols.
  • a process for shielding a radioactive area to prevent the escape therefrom of neutron radiation which comprises applying to such area a settable viscous, puttylike composition consisting essentially of an intimate mixture of from 0.5% to 10% by weight of boron carbide and from 10% to 85% by weight of finely divided polyethylene, and a fluid resinous carrier selected from at least one of the group consisting of fluid polyesters, epoxy resins, castable phenol-aldehyde resins, butadiene polymers and copolymers thereof with styrene, butadieneacrylonitrile copolymers and plastisols, and curing said composition to a solid, said solid composition serving to attenuate fast moving neutrons and capture slow moving neutrons.
  • An article of manufacture comprising a member adapted to carry radioactive material and a body of molded, solid radiation shielding material applied thereto, said shielding material being adapted to attenuate fast moving neutrons and capture slow moving neutrons and consisting essentially of, in combination, an intimate mixture of (a) a compound having a ratio of hydrogen atoms to all other atoms therein within the range of from 0.5:1 to 2:1 and being selected from at least one of the group consisting of polyethylene, butyl rubber, paraffin, polyiso butylene, and polyisoprene, (b) and from 0.5% to 10% by weight of boron in (c) a carrier selected from at least one of the group consisting of fluid polyesters, epoxy resins, castable phenol-aldehyde resins, butadiene polymers and copolymers thereof with styrene, butadieneacrylonitrile copolymers and plastisols.

Landscapes

  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Chemical & Material Sciences (AREA)
  • Dispersion Chemistry (AREA)
  • Sealing Material Composition (AREA)
US620147A 1956-11-02 1956-11-02 Settable neutron radiation shielding material Expired - Lifetime US2961415A (en)

Priority Applications (2)

Application Number Priority Date Filing Date Title
BE567962D BE567962A (de) 1956-11-02
US620147A US2961415A (en) 1956-11-02 1956-11-02 Settable neutron radiation shielding material

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
US620147A US2961415A (en) 1956-11-02 1956-11-02 Settable neutron radiation shielding material

Publications (1)

Publication Number Publication Date
US2961415A true US2961415A (en) 1960-11-22

Family

ID=24484779

Family Applications (1)

Application Number Title Priority Date Filing Date
US620147A Expired - Lifetime US2961415A (en) 1956-11-02 1956-11-02 Settable neutron radiation shielding material

Country Status (2)

Country Link
US (1) US2961415A (de)
BE (1) BE567962A (de)

Cited By (38)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3075925A (en) * 1960-12-21 1963-01-29 Harold L Dunegan Radiation shielding composition
US3106535A (en) * 1959-08-24 1963-10-08 Ici Ltd Neutron radiation shielding material
US3123576A (en) * 1964-03-03 Rare earth shield
US3133887A (en) * 1958-10-06 1964-05-19 Norton Co Neutron shields and methods of manufacturing them
US3142649A (en) * 1959-12-28 1964-07-28 Ici Ltd Neutron radiation shielding material
US3161606A (en) * 1960-08-11 1964-12-15 Eastman Kodak Co Polyethylene neutron shield containing dispersed boric oxide
US3200085A (en) * 1959-03-02 1965-08-10 Arthur L Barber Jr Radiation barrier material and method of making the same
US3203906A (en) * 1959-08-10 1965-08-31 Borax Cons Ltd Bituminous shielding composition
US3231521A (en) * 1961-05-24 1966-01-25 Carborundum Co Neutron shielding using a composition comprising graphite, boron carbide and carbonized residue
US3246157A (en) * 1962-07-12 1966-04-12 Atlantic Refining Co Shielding system for a chlorine logging apparatus
US3247131A (en) * 1963-04-04 1966-04-19 Union Carbide Corp Neutron shielding composition having good high temperature strength
US3261800A (en) * 1960-09-08 1966-07-19 Du Pont Boron nitride incorporated in polymer products
US3280329A (en) * 1962-08-08 1966-10-18 Dow Chemical Co Process for controlling thermal neutron concentration in an irradiated system
US3389258A (en) * 1964-07-22 1968-06-18 Atlantic Richfield Co Shielding array for chlorine logging sonde utilizing neutron and gamma ray shielding elements
US3437602A (en) * 1966-11-25 1969-04-08 Irving Tashlick Radiation shielding material and method of making same
FR2055982A5 (en) * 1969-08-13 1971-05-14 Transnucleaire Storage and transport container for a - radioactive materials
US3780306A (en) * 1971-05-27 1973-12-18 Nat Lead Co Radioactive shipping container with neutron and gamma absorbers
US3858050A (en) * 1972-09-29 1974-12-31 Kewanee Oil Co Electrically insulating gamma radiation shield
US4213883A (en) * 1977-12-30 1980-07-22 The Carborundum Company Method for manufacture of neutron absorbing articles
US4287145A (en) * 1977-11-25 1981-09-01 Kennecott Corporation Method for manufacturing neutron absorbing article
FR2534058A1 (fr) * 1982-10-04 1984-04-06 Guibert Jacques Revetement projetable antineutronique
FR2546331A1 (fr) * 1983-05-20 1984-11-23 Robatel Slpi Perfectionnements aux materiaux hydrogenes de protection antineutronique
FR2556876A1 (fr) * 1983-12-14 1985-06-21 Centre Nat Etd Spatiales Procede de fabrication de structures en materiaux composites formant blindage neutronique
US4575578A (en) * 1983-01-05 1986-03-11 Keene Corporation Radiation shielding and thermally conductive gasket with internal bonding agent
US4684480A (en) * 1984-01-31 1987-08-04 Elektroschmelzwerk Kempten Gmbh Ceramic bonded neutron absorber plates of boron carbide and free carbon
US5084234A (en) * 1988-12-31 1992-01-28 Hoesgen Karlheinz Absorption casing for a source of radioactive radiation, particularly for a nuclear reactor
US5616928A (en) * 1977-04-13 1997-04-01 Russell; Virginia Protecting personnel and the environment from radioactive emissions by controlling such emissions and safely disposing of their energy
EP1316968A2 (de) * 2001-11-30 2003-06-04 Hitachi, Ltd. Nerutronenabschirmungsmaterialien und Behälter für verbrauchten Brennstoff
US20040127599A1 (en) * 2002-10-25 2004-07-01 Pascale Abadie Meterial for neutron shielding and for maintaining sub-criticality, process for its preparation and its applications
US20050001205A1 (en) * 2001-10-01 2005-01-06 Pierre Malalel Neutron shielding material for maintaining sub-criticality based on unsaturated polymer
US20050012054A1 (en) * 2001-12-12 2005-01-20 Martine Valiere Material for neutron shielding and for maintaining sub-criticality based on vinylester resin
WO2009042944A1 (en) * 2007-09-28 2009-04-02 Hybrid Plastics, Inc. Neutron shielding composition
US20090085011A1 (en) * 2003-12-18 2009-04-02 Lichtenhan Joseph D Neutron shielding composition
FR2925753A1 (fr) * 2007-12-21 2009-06-26 Commissariat Energie Atomique Dispositif et procede pour le conditionnement de dechets nucleaires
RU2561989C1 (ru) * 2014-07-17 2015-09-10 Федеральное государственное автономное образовательное учреждение высшего профессионального образования "Национальный исследовательский технологический университет "МИСиС" Радиационно-защитный материал на полимерной основе с повышенными рентгенозащитными и нейтронозащитными свойствами
WO2017030577A1 (en) * 2015-08-19 2017-02-23 Danny Warren Composition for radiation shielding
US10878974B2 (en) 2018-12-14 2020-12-29 Rad Technology Medical Systems, Llc Shielding facility and method of making thereof
US20210360841A1 (en) * 2010-07-28 2021-11-18 United States Of America As Represented By The Administrator Of Nasa Methods of making z-shielding

Families Citing this family (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
AT320092B (de) * 1969-03-14 1975-01-27 Tatabanyai Szenbanyak Präparat und Verfahren zum Schutz gegen Neutronenstrahlung
FR2485788A1 (fr) * 1980-06-27 1981-12-31 Poujaud Edouard Materiau destine a la confection des blindages antiradiations

Citations (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US2162178A (en) * 1937-01-19 1939-06-13 Du Pont Film Mfg Corp X-ray shielding compound
US2796411A (en) * 1947-01-29 1957-06-18 Raymond E Zirkle Radiation shield

Patent Citations (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US2162178A (en) * 1937-01-19 1939-06-13 Du Pont Film Mfg Corp X-ray shielding compound
GB513838A (en) * 1937-01-19 1939-10-23 Du Pont Film Mfg Corp Improvements in and relating to x-ray shielding materials
US2796411A (en) * 1947-01-29 1957-06-18 Raymond E Zirkle Radiation shield

Cited By (48)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3123576A (en) * 1964-03-03 Rare earth shield
US3133887A (en) * 1958-10-06 1964-05-19 Norton Co Neutron shields and methods of manufacturing them
US3200085A (en) * 1959-03-02 1965-08-10 Arthur L Barber Jr Radiation barrier material and method of making the same
US3203906A (en) * 1959-08-10 1965-08-31 Borax Cons Ltd Bituminous shielding composition
US3106535A (en) * 1959-08-24 1963-10-08 Ici Ltd Neutron radiation shielding material
US3142649A (en) * 1959-12-28 1964-07-28 Ici Ltd Neutron radiation shielding material
US3161606A (en) * 1960-08-11 1964-12-15 Eastman Kodak Co Polyethylene neutron shield containing dispersed boric oxide
US3261800A (en) * 1960-09-08 1966-07-19 Du Pont Boron nitride incorporated in polymer products
US3075925A (en) * 1960-12-21 1963-01-29 Harold L Dunegan Radiation shielding composition
US3231521A (en) * 1961-05-24 1966-01-25 Carborundum Co Neutron shielding using a composition comprising graphite, boron carbide and carbonized residue
US3246157A (en) * 1962-07-12 1966-04-12 Atlantic Refining Co Shielding system for a chlorine logging apparatus
US3280329A (en) * 1962-08-08 1966-10-18 Dow Chemical Co Process for controlling thermal neutron concentration in an irradiated system
US3247131A (en) * 1963-04-04 1966-04-19 Union Carbide Corp Neutron shielding composition having good high temperature strength
US3389258A (en) * 1964-07-22 1968-06-18 Atlantic Richfield Co Shielding array for chlorine logging sonde utilizing neutron and gamma ray shielding elements
US3437602A (en) * 1966-11-25 1969-04-08 Irving Tashlick Radiation shielding material and method of making same
FR2055982A5 (en) * 1969-08-13 1971-05-14 Transnucleaire Storage and transport container for a - radioactive materials
US3780306A (en) * 1971-05-27 1973-12-18 Nat Lead Co Radioactive shipping container with neutron and gamma absorbers
US3858050A (en) * 1972-09-29 1974-12-31 Kewanee Oil Co Electrically insulating gamma radiation shield
US5616928A (en) * 1977-04-13 1997-04-01 Russell; Virginia Protecting personnel and the environment from radioactive emissions by controlling such emissions and safely disposing of their energy
US4287145A (en) * 1977-11-25 1981-09-01 Kennecott Corporation Method for manufacturing neutron absorbing article
US4213883A (en) * 1977-12-30 1980-07-22 The Carborundum Company Method for manufacture of neutron absorbing articles
FR2534058A1 (fr) * 1982-10-04 1984-04-06 Guibert Jacques Revetement projetable antineutronique
US4575578A (en) * 1983-01-05 1986-03-11 Keene Corporation Radiation shielding and thermally conductive gasket with internal bonding agent
FR2546331A1 (fr) * 1983-05-20 1984-11-23 Robatel Slpi Perfectionnements aux materiaux hydrogenes de protection antineutronique
FR2556876A1 (fr) * 1983-12-14 1985-06-21 Centre Nat Etd Spatiales Procede de fabrication de structures en materiaux composites formant blindage neutronique
US4684480A (en) * 1984-01-31 1987-08-04 Elektroschmelzwerk Kempten Gmbh Ceramic bonded neutron absorber plates of boron carbide and free carbon
US5084234A (en) * 1988-12-31 1992-01-28 Hoesgen Karlheinz Absorption casing for a source of radioactive radiation, particularly for a nuclear reactor
US20050001205A1 (en) * 2001-10-01 2005-01-06 Pierre Malalel Neutron shielding material for maintaining sub-criticality based on unsaturated polymer
US7524438B2 (en) 2001-10-01 2009-04-28 Cogema Logistics Unsaturated polyester-based material for neutron-shielding and for maintaining sub-criticality
EP1316968A2 (de) * 2001-11-30 2003-06-04 Hitachi, Ltd. Nerutronenabschirmungsmaterialien und Behälter für verbrauchten Brennstoff
EP1316968A3 (de) * 2001-11-30 2003-09-03 Hitachi, Ltd. Nerutronenabschirmungsmaterialien und Behälter für verbrauchten Brennstoff
US6797972B2 (en) 2001-11-30 2004-09-28 Hitachi, Ltd. Neutron shielding materials and a cask for spent fuel
US20050012054A1 (en) * 2001-12-12 2005-01-20 Martine Valiere Material for neutron shielding and for maintaining sub-criticality based on vinylester resin
US7160486B2 (en) * 2001-12-12 2007-01-09 Cogema Logistics Material based on vinylester resin for neutron shielding and maintenance of sub-criticality
US20040127599A1 (en) * 2002-10-25 2004-07-01 Pascale Abadie Meterial for neutron shielding and for maintaining sub-criticality, process for its preparation and its applications
US7399431B2 (en) 2002-10-25 2008-07-15 Cogema Logistics Material for neutron shielding and for maintaining sub-critically, process for its preparation and its applications
US20090085011A1 (en) * 2003-12-18 2009-04-02 Lichtenhan Joseph D Neutron shielding composition
WO2009042944A1 (en) * 2007-09-28 2009-04-02 Hybrid Plastics, Inc. Neutron shielding composition
FR2925753A1 (fr) * 2007-12-21 2009-06-26 Commissariat Energie Atomique Dispositif et procede pour le conditionnement de dechets nucleaires
WO2009106730A2 (fr) * 2007-12-21 2009-09-03 Commissariat A L'energie Atomique Dispositif et procede pour le conditionnement de dechets nucleaires
WO2009106730A3 (fr) * 2007-12-21 2009-11-26 Commissariat A L'energie Atomique Dispositif et procede pour le conditionnement de dechets nucleaires
US20210360841A1 (en) * 2010-07-28 2021-11-18 United States Of America As Represented By The Administrator Of Nasa Methods of making z-shielding
RU2561989C1 (ru) * 2014-07-17 2015-09-10 Федеральное государственное автономное образовательное учреждение высшего профессионального образования "Национальный исследовательский технологический университет "МИСиС" Радиационно-защитный материал на полимерной основе с повышенными рентгенозащитными и нейтронозащитными свойствами
WO2017030577A1 (en) * 2015-08-19 2017-02-23 Danny Warren Composition for radiation shielding
US10878974B2 (en) 2018-12-14 2020-12-29 Rad Technology Medical Systems, Llc Shielding facility and method of making thereof
US11437160B2 (en) 2018-12-14 2022-09-06 Rad Technology Medical Systems, Llc Shielding facility and methods of making thereof
US11545275B2 (en) 2018-12-14 2023-01-03 Rad Technology Medical Systems Llc Shielding facility and methods of making thereof
US12073954B2 (en) 2018-12-14 2024-08-27 Rad Technology Medical Systems Llc Shielding facility and method of making thereof

Also Published As

Publication number Publication date
BE567962A (de)

Similar Documents

Publication Publication Date Title
US2961415A (en) Settable neutron radiation shielding material
TW201019347A (en) Waste storage vessels and compositions therefor
US3609372A (en) Shaped polymeric shield against neutron and gamma radiation
Leonardi et al. A study on natural radioactivity and radon exhalation rate in building materials containing norm residues: preliminary results
US4437013A (en) Neutron and gamma radiation shielding material, structure, and process of making structure
Wagh et al. Durability and shielding performance of borated Ceramicrete coatings in beta and gamma radiation fields
TW200426855A (en) Amorphous composition for high level radiation and environmental protection
KR101712879B1 (ko) 원전 1차 방호벽의 중성자 차폐를 위한 콘크리트 및 그 제조방법
US3106535A (en) Neutron radiation shielding material
US3213031A (en) Method of sealing refractory vessel containing radioactive wastes
JPS5933874B2 (ja) 中性子遮蔽材
AU630202B2 (en) Improvements in or relating to thermally resistant materials
US3238148A (en) Shielding concrete and aggregates
JPS6253080B2 (de)
JPS5942280B2 (ja) 放射線遮蔽材
US4261756A (en) Lead alloy and granulate concrete containing the same
US3827982A (en) Moldable lead composition
US5946639A (en) In-situ stabilization of radioactive zirconium swarf
US3328338A (en) Composition of matter and method of preparation
JP2015152464A (ja) 放射線遮蔽体及び放射線遮蔽構造
JP2015152463A (ja) 放射線遮蔽体及び放射線遮蔽構造
JPH01292294A (ja) 放射線遮蔽用アスファルト組成物
JPS6218040B2 (de)
KR100298037B1 (ko) 에폭시수지계중성자차폐재조성물
Chen et al. Design of a remote sprayed fast-curing γ-radiation-shielding material used in the collection of the leaked radioactive waste