CA1096974A - Device for the storage or disposal of radioactive wastes - Google Patents
Device for the storage or disposal of radioactive wastesInfo
- Publication number
- CA1096974A CA1096974A CA296,091A CA296091A CA1096974A CA 1096974 A CA1096974 A CA 1096974A CA 296091 A CA296091 A CA 296091A CA 1096974 A CA1096974 A CA 1096974A
- Authority
- CA
- Canada
- Prior art keywords
- receptacle
- receptacles
- radiation
- system defined
- outer receptacle
- 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
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- Processing Of Solid Wastes (AREA)
Abstract
ABSTRACT OF THE DISCLOSURE
A container for the ultimate disposal of radioactive wastes comprises an outer receptacle of standard size and interchangeable inner receptacles receivable in the outer receptacle and provided with spacers for centering the inner receptacle within the outer receptacle. For radioactive waste with reduced radioactivity, a larger receptacle containing a larger quantity of the waste can be disposed within the outer receptacle whereas, for more highly radioactive waste, a smaller receptacle containing smaller quantities of the radioactive waste can be disposed within the outer receptacle. The space between the two receptacles is filled with a substance capable of absorbing radiation from the inner receptacle, i.e. a radia-tion absorber or shielding material.
A container for the ultimate disposal of radioactive wastes comprises an outer receptacle of standard size and interchangeable inner receptacles receivable in the outer receptacle and provided with spacers for centering the inner receptacle within the outer receptacle. For radioactive waste with reduced radioactivity, a larger receptacle containing a larger quantity of the waste can be disposed within the outer receptacle whereas, for more highly radioactive waste, a smaller receptacle containing smaller quantities of the radioactive waste can be disposed within the outer receptacle. The space between the two receptacles is filled with a substance capable of absorbing radiation from the inner receptacle, i.e. a radia-tion absorber or shielding material.
Description
~96~7~
DEVICE FOR T~ STORAGE OR DISPOSAL
OF RADIOACTIVE I~STES
SPECIFIGATION
~ Field of the Invention .: me present invenkion relates to a device for the `; ultimate disposal of radioactive waste and, more particularly, for radioactive nuclear power plant wastes.
Back~round of the Inventi_n , In the disposal of radioactive wastes and particularly lV the disposal of radioactive nuclear power plant wastes or . . .
.- wastes derived Erom reprocessing plants or nuclear fuels and .. the like, it is conventional practice to provide standardized -:
` containers or receptacles having a predetermined shielding ;
characteristic, in the interior o~ which the radioactive wastes are stored and which can be depos.ited for ultimate disposal of .~ , , ... sueh wastes.
:.` Because of industrial or ~overnment standardization, ,: - .
the customary practice is to provide standardized containers, i.e. containers with predetermined degrees of radioactive shielding, for the various types of wastes which may be pro-duced or may have to be disposed of.
;~ Natural.ly, such standardized containers cannot be used for radioaet:ive wastes of different potency, i.e. a ~.
different degree of radioactivity. Thus, when radioactive wastes are generated which have greater or lesser radioactivity, : it is necessary to provide standardized containers for these ,, . .... ~ .. .. ~. .... ,- . . . . . . . .
~96g~L
particular ma~erials. For instance, when more highly radio~
active wastes are to be disposed of, one normally uses a standardized container having a greater degree of shieldin~, iOe. a thicker shielding layer. t'onversely, when radioac~ive wastes of reduced radioactiviky are to be considere~, a lesser degree o~ shielding may be required.
As a consequence, indust:rial or governrnenk standard- ;
ization has resulted in the requirement that the ir-stallation generating such radioactive wastes must keep on hancl a mlmber of different standardi~ed containers having difEerent degrees of shielding for optimum disposal of radioactive wastes oE
different radiation intensitiesO This, of course, poses the problem for a nuclear power plant or an installation or re-processing nuclear fuels since a large number o containers of different dimensions and s'nielding capabilities must be provided.
Objects of _he Invention It is a principal object of the present invention to provide a radioactive-waste disposal system which obviates these disadvantages.
Another object of the invention is to provide a device for ~he ul~imate disposal of radioactive wastes which ; enables ~he shielding of radioactive materials of different radiation intensities in accordance with industrial or govern-ment standards without requiring a lar~e number of rela-tively massive containers of different dimensions to be stored or provided.
~0~6974~
Summary of the Inv _ t-on These ~bjects and others which will become apparent l~ereinafter are attained, in accordance with the present inven-tion7 in a system Eor the inal disposal of radioactive wastes which comprises an outer receptacle of given dirnensions and wall t~ickness, an assortment o~ inner receptacles o~ different capacity and sizes, depending upon the intenslty of the radio-active waste to be disposed of, the inner receptacle being ; spacedly received interchangeably in th~ outer receptacle, and a body of shielding material filling the space between the receptacles.
For radioactive wastes of reduced intensity, the inner receptacle can be of larger vol~ne and capacity o~ size so that the walls of this inner receptacle more closely approach the walls o~ the outer receptacle. On the other hand, ~or radioactive wastes of greater intensity, the inner receptacle ~,i will have a smaller capacity and size and thus be spaced, by the aforen~entioned spacer means, more distantly from the walls of the outer receptacle. As noted, the outer receptacle can be a given size For an assortment oE inner receptacles.
Naturally~ when a smaller inner receptacle is centered within the ou~er receptacle, the space between the ~wo recep-tacles is filled witll a greater thickness of the shielding material so that the pac~age is capable of intercepting radio-activ~ty of greater intensity.
According to a feature of the invention, the spacer means is provided directly upon the inner receptacle and ~e spacing element of the spacer means can have a greater lengtl for the smaller irmer receptacl~ and a reduced length for ~he larger inner receptacle, thereby ensuring a greater spacing 697~
be-~ween the walls of the recep~acles when the raclioactivlty oE
grea~er intensiky is involved.
The invention derives from the recognition that the standard normally applied to the disposal of radioactive wastes requires that a package af~ord a greater degree of shielding and hence a greater thickness of shielding ma~erials for radio-active wastes of higher activity than for radioactive wastes of lower activity.
This greater shielding in the case of radioactive wastes of greater intensity is achieved by spacing the inner Gr auxiliary receptacle more distantly Erom the wall of the outer receptacle which can have a given thickness, the space between the two receptacles being filled with a grea~er thick-- ness of the shielding material.
It is thus possible, ~or an outer receptacle of given dimensions, to accommodate radioactive wastes of a wide variety of radiation intensities simply by using the selected one of the assortment o~ interchangeable inner recep~acles which is approprlatP ~hereto. By using the smaller receptacle with ~the longer spaces for the radioactive wastes of greater intensity~ it is possible to automatically increase the spacing between ~he walls of the two receptacles and hence increase the thickness of the shielding material interposed between the walls of the two receptacles.
The auxiliary or inner receptacle can have a releas-able or removable cover which is fixed permanently to the remainder of the receptacle. Naturally, when a removable cover is provided upon the auxiliary receptacle or the inner receptacle ~ disposed within the outer receptacle without a cover, a greater thickness of the shielding material must be provided between the top of t'ne radioactive material within 3L~;)9697~
the inner receptacle and the cover.
The outer receptacle rnay also be provided with a permanently attached or removable cover as desired.
According to a feature o~ the invention, the space between receptacles is also used t:o accommodate means for treating radioactive wastes within the inner~receptacle. It is fre~uently desirable to subject: the radioackive wastes to a hea~ing treatment to evacuate moisture therefrom or to carry out a setting operation. To this end~ there can be provided, in accordance with the feature of the invention, within the space between the receptacles, removable or ~er~anently em-placed heating rods or tubes traversed by heating fluid which can raise the radioactive wastes to a degasification or vapor-ization temperature.
The heating means within the space can also be used to ensure thorough fus~on of the ~ ing material which is disposed between the receptacles, e.g. when the filling material is to be liquefied and later solidified in place.
The advanta~es of the system of the present invention include the ability to provide a single outer receptacle ~or radioactive wastes of a wide range of radioactivities while maintaining the necessary shielding standards.
A nuclear power plant or institute or ot'ner establish-ment for supplying nuclear fuels to nuclear power plants or for reprocessing the ~uels of nuclear power plants, no longer must stock large nu~bers of massive receptacles of different standard radioactive shielding capacities. ~le introduction o~ radio-active wastes into the package of the present invention can be accomplished readily and by conventional processes.
~0~9~4 rief ~ ion of the Drawing The above and other objec-ts, eatures and advantages of the present invention will become ~ore readily apparent :Erom the following description, re:Eerence being made to the accompanying drawing in whlch:
IG, 1 is a vertical cross-sectional view through a package or the final disposal of radioactive wastes accord-ing to the invention; ~:~
FIG. 2 is a similar view of a package for the dis-posal of radioactive wastes of lesser radiation intensity9 FIG. 3 is a.cross-sectional view taken along the line III - III of FIG. 1, but showing the package with the shielding filling material omitted;
FIG. 4 is a detail view showing one mode of attach-ment of the cover of the outer receptacle to the remainder thereof;
FIG. 5 is a detail view similar to FIG. 4 illustrat-ing another embodiment of the invention; and FIG. 6 is another detail view similar to FIG. 4 showing yet another embodiment of the invention.
c ~escriJ~
The device illustrated in FIGS. 1 - 3 of the drawing is provided for the disposal of radioactive wastes A, especially for radioactive nuclear power plant wastes.
The device essentially comprises an outer receptacle
DEVICE FOR T~ STORAGE OR DISPOSAL
OF RADIOACTIVE I~STES
SPECIFIGATION
~ Field of the Invention .: me present invenkion relates to a device for the `; ultimate disposal of radioactive waste and, more particularly, for radioactive nuclear power plant wastes.
Back~round of the Inventi_n , In the disposal of radioactive wastes and particularly lV the disposal of radioactive nuclear power plant wastes or . . .
.- wastes derived Erom reprocessing plants or nuclear fuels and .. the like, it is conventional practice to provide standardized -:
` containers or receptacles having a predetermined shielding ;
characteristic, in the interior o~ which the radioactive wastes are stored and which can be depos.ited for ultimate disposal of .~ , , ... sueh wastes.
:.` Because of industrial or ~overnment standardization, ,: - .
the customary practice is to provide standardized containers, i.e. containers with predetermined degrees of radioactive shielding, for the various types of wastes which may be pro-duced or may have to be disposed of.
;~ Natural.ly, such standardized containers cannot be used for radioaet:ive wastes of different potency, i.e. a ~.
different degree of radioactivity. Thus, when radioactive wastes are generated which have greater or lesser radioactivity, : it is necessary to provide standardized containers for these ,, . .... ~ .. .. ~. .... ,- . . . . . . . .
~96g~L
particular ma~erials. For instance, when more highly radio~
active wastes are to be disposed of, one normally uses a standardized container having a greater degree of shieldin~, iOe. a thicker shielding layer. t'onversely, when radioac~ive wastes of reduced radioactiviky are to be considere~, a lesser degree o~ shielding may be required.
As a consequence, indust:rial or governrnenk standard- ;
ization has resulted in the requirement that the ir-stallation generating such radioactive wastes must keep on hancl a mlmber of different standardi~ed containers having difEerent degrees of shielding for optimum disposal of radioactive wastes oE
different radiation intensitiesO This, of course, poses the problem for a nuclear power plant or an installation or re-processing nuclear fuels since a large number o containers of different dimensions and s'nielding capabilities must be provided.
Objects of _he Invention It is a principal object of the present invention to provide a radioactive-waste disposal system which obviates these disadvantages.
Another object of the invention is to provide a device for ~he ul~imate disposal of radioactive wastes which ; enables ~he shielding of radioactive materials of different radiation intensities in accordance with industrial or govern-ment standards without requiring a lar~e number of rela-tively massive containers of different dimensions to be stored or provided.
~0~6974~
Summary of the Inv _ t-on These ~bjects and others which will become apparent l~ereinafter are attained, in accordance with the present inven-tion7 in a system Eor the inal disposal of radioactive wastes which comprises an outer receptacle of given dirnensions and wall t~ickness, an assortment o~ inner receptacles o~ different capacity and sizes, depending upon the intenslty of the radio-active waste to be disposed of, the inner receptacle being ; spacedly received interchangeably in th~ outer receptacle, and a body of shielding material filling the space between the receptacles.
For radioactive wastes of reduced intensity, the inner receptacle can be of larger vol~ne and capacity o~ size so that the walls of this inner receptacle more closely approach the walls o~ the outer receptacle. On the other hand, ~or radioactive wastes of greater intensity, the inner receptacle ~,i will have a smaller capacity and size and thus be spaced, by the aforen~entioned spacer means, more distantly from the walls of the outer receptacle. As noted, the outer receptacle can be a given size For an assortment oE inner receptacles.
Naturally~ when a smaller inner receptacle is centered within the ou~er receptacle, the space between the ~wo recep-tacles is filled witll a greater thickness of the shielding material so that the pac~age is capable of intercepting radio-activ~ty of greater intensity.
According to a feature of the invention, the spacer means is provided directly upon the inner receptacle and ~e spacing element of the spacer means can have a greater lengtl for the smaller irmer receptacl~ and a reduced length for ~he larger inner receptacle, thereby ensuring a greater spacing 697~
be-~ween the walls of the recep~acles when the raclioactivlty oE
grea~er intensiky is involved.
The invention derives from the recognition that the standard normally applied to the disposal of radioactive wastes requires that a package af~ord a greater degree of shielding and hence a greater thickness of shielding ma~erials for radio-active wastes of higher activity than for radioactive wastes of lower activity.
This greater shielding in the case of radioactive wastes of greater intensity is achieved by spacing the inner Gr auxiliary receptacle more distantly Erom the wall of the outer receptacle which can have a given thickness, the space between the two receptacles being filled with a grea~er thick-- ness of the shielding material.
It is thus possible, ~or an outer receptacle of given dimensions, to accommodate radioactive wastes of a wide variety of radiation intensities simply by using the selected one of the assortment o~ interchangeable inner recep~acles which is approprlatP ~hereto. By using the smaller receptacle with ~the longer spaces for the radioactive wastes of greater intensity~ it is possible to automatically increase the spacing between ~he walls of the two receptacles and hence increase the thickness of the shielding material interposed between the walls of the two receptacles.
The auxiliary or inner receptacle can have a releas-able or removable cover which is fixed permanently to the remainder of the receptacle. Naturally, when a removable cover is provided upon the auxiliary receptacle or the inner receptacle ~ disposed within the outer receptacle without a cover, a greater thickness of the shielding material must be provided between the top of t'ne radioactive material within 3L~;)9697~
the inner receptacle and the cover.
The outer receptacle rnay also be provided with a permanently attached or removable cover as desired.
According to a feature o~ the invention, the space between receptacles is also used t:o accommodate means for treating radioactive wastes within the inner~receptacle. It is fre~uently desirable to subject: the radioackive wastes to a hea~ing treatment to evacuate moisture therefrom or to carry out a setting operation. To this end~ there can be provided, in accordance with the feature of the invention, within the space between the receptacles, removable or ~er~anently em-placed heating rods or tubes traversed by heating fluid which can raise the radioactive wastes to a degasification or vapor-ization temperature.
The heating means within the space can also be used to ensure thorough fus~on of the ~ ing material which is disposed between the receptacles, e.g. when the filling material is to be liquefied and later solidified in place.
The advanta~es of the system of the present invention include the ability to provide a single outer receptacle ~or radioactive wastes of a wide range of radioactivities while maintaining the necessary shielding standards.
A nuclear power plant or institute or ot'ner establish-ment for supplying nuclear fuels to nuclear power plants or for reprocessing the ~uels of nuclear power plants, no longer must stock large nu~bers of massive receptacles of different standard radioactive shielding capacities. ~le introduction o~ radio-active wastes into the package of the present invention can be accomplished readily and by conventional processes.
~0~9~4 rief ~ ion of the Drawing The above and other objec-ts, eatures and advantages of the present invention will become ~ore readily apparent :Erom the following description, re:Eerence being made to the accompanying drawing in whlch:
IG, 1 is a vertical cross-sectional view through a package or the final disposal of radioactive wastes accord-ing to the invention; ~:~
FIG. 2 is a similar view of a package for the dis-posal of radioactive wastes of lesser radiation intensity9 FIG. 3 is a.cross-sectional view taken along the line III - III of FIG. 1, but showing the package with the shielding filling material omitted;
FIG. 4 is a detail view showing one mode of attach-ment of the cover of the outer receptacle to the remainder thereof;
FIG. 5 is a detail view similar to FIG. 4 illustrat-ing another embodiment of the invention; and FIG. 6 is another detail view similar to FIG. 4 showing yet another embodiment of the invention.
c ~escriJ~
The device illustrated in FIGS. 1 - 3 of the drawing is provided for the disposal of radioactive wastes A, especially for radioactive nuclear power plant wastes.
The device essentially comprises an outer receptacle
2 having standardiæed dimensions and radioactive shielding capacity and preferably composed of a radioactive shielding ; material such as concrete which can be reinforced~ e.g~ via :~ :
the reinforcing rods represented at 2a, The outer receptacle 2 is formed with an upwardly open lower cont~iner 2e wllich can be formed with eyes 2b enabling th~ con~ainer and the entire package to be lifted by a crane.
The mouth of the container 2e is stepped as shown at 2b to be tightly itted with a complementaril~ stepped cover 2c which can be permanently secured to the container 2e with an adhesive or by an additional layer of concrete.
Tne outer ~eceptacle 2 is provided with an interior space 3 which receives ~he radioactive waste A in an inner receptacle 1 which can have a relatively thin wall which also has some shielding function. ~ cover la can be pe~m!anently affixed to or removable from the inner receptacle 1.
According to ~he invention, the inner receptacle 1 is provided with lateral spacing arms 5 and downwardly extending spacing arms 5a dimensionecl to center the radioactive-waste enclosure wi~hin the chamber 3.
As can be seen by a comparison of FIGS. 1 and 2, a number of replaceable or intercha~geable receptacles 1 and 1' can be provided and the arms 5, Sa or 5', 5a' can be correspond-ingly dimensioned to ensure an appropriate centering of which-ever receptacle 1 or 1' is selected.
The space between the receptacles, i.e~ t~e chamber
the reinforcing rods represented at 2a, The outer receptacle 2 is formed with an upwardly open lower cont~iner 2e wllich can be formed with eyes 2b enabling th~ con~ainer and the entire package to be lifted by a crane.
The mouth of the container 2e is stepped as shown at 2b to be tightly itted with a complementaril~ stepped cover 2c which can be permanently secured to the container 2e with an adhesive or by an additional layer of concrete.
Tne outer ~eceptacle 2 is provided with an interior space 3 which receives ~he radioactive waste A in an inner receptacle 1 which can have a relatively thin wall which also has some shielding function. ~ cover la can be pe~m!anently affixed to or removable from the inner receptacle 1.
According to ~he invention, the inner receptacle 1 is provided with lateral spacing arms 5 and downwardly extending spacing arms 5a dimensionecl to center the radioactive-waste enclosure wi~hin the chamber 3.
As can be seen by a comparison of FIGS. 1 and 2, a number of replaceable or intercha~geable receptacles 1 and 1' can be provided and the arms 5, Sa or 5', 5a' can be correspond-ingly dimensioned to ensure an appropriate centering of which-ever receptacle 1 or 1' is selected.
The space between the receptacles, i.e~ t~e chamber
3 which is not occupied by the receptacle 1 or 1', is filled with a mass 4 OI shielding material. Thi5 mass 4 can be constitu~ed by mol~en lead or a pulverulent shielding material such as, for exaople, a lead-containing mineral~ Other materials of high neutron cross-sectiong eOg. bitumen or paraf-fin can also be used, depending upon the radiation-shielding standard involved.
, :
~og6974 As is also apparent from FIGS. 1 and 2, a srnaller receptacle 1 is employed when the radioactive substance A has a hîgher radiation intensity. A l~rger receptacle is used as sho~m at 1' when the radiation intensity of the radioactive waste A' is less. In the case of higher intensity~ therefore, a greater thickness of the shielding material ~ is provided.
A tube lb may open into the receptacle, a correspond-ing tube lb' being provided in the case of the embodiment of FIG. 2, to fill the radioactive material into the inner recep-tacle. Alternatively, the tubes lb and lb' may be eliminated when the receptacle 1 or 1' is filled prior to its insertion into the outer recep-tacle 2.
As sh~wn in FIG. 1, the space 3 may also be provided ~
with heating rods 8 or other treating meansfor subjecting ~he ~`
radioactive wastes to evaporation or other -thermal treatment~
The hea~ing rods may also be used, if desired, to melt the shielding material 4 and ensure a complete distribut~on of the ~;shielding material 4 within the space 3 without air bubbles or the like. The heating rods 8 are lost within the body of the shielding 4 and become part of the package.
In the embodiment of FIGS. 1 and 2, the walls of ~he inner and outer receptacles are formed with rods 7 and 7' which project into the material 4 and serve to anchor the material ~f and the receptacle 1'.
The receptacle 1 and the receptacle 2 can be provided with passa~es 6 and 6' for venting the gases from the package during the E;lling or heating operations or to serve as filling passages. The tubes lb and lb' and the passages ~ and 6' are ultimately filled with radiation shielding material. ~ore particularly? the passages 6 can serve ~or pumping material into the package or evacuating vapors therefrom. A ~aterial capable ,~
~3 .
69~7~
of encapsulating the radioac~ive wastes and hardening insicle the tube, e.g. liquid bitumen, can also be introduced through the passages ~ in which case the liquid bitu~en can ultimately fill these passagesO
As can be seen from FIG. 4, the cover 10 for the outer receptacle 14 can be complementarily stepped at 12 to fit tightly upon the mouth 13 of the outer receptacle 14. In this caseeye 18 is affixed ko the outer receptacle 14 while bolts 1~ attached to plates 17 may be embedded in the concrete of the container 14 so that nuts 15 can be threaded onto the bolts 1~ to secure the cover 10 in place, An alternative construction has been shown in FI~. 5 in which the bolts lh receive nuts 19 which are also formed with necks 20 to which the e~es 21 are secured. In this case, the cover-securing means is also provided with lifting eyes to enable the package to be moved by a crane, In the e~bodiment of FIG. ~, the eye 22 is formed as a nut 23 on a bolt 24 swingable on a lug 25 about a pen 2~ anchored in the container 27 and within a slot 28 thereof. When the lug is swung in the counterclockwise sense into a slot 29 of the cover 30, the nut 23 may be tightened to clamp the cover in place.
In place of the heating rods 8, heating means such as tubes through which a heating fluid can be circulated, can be received in the chamber 3.
_9_
, :
~og6974 As is also apparent from FIGS. 1 and 2, a srnaller receptacle 1 is employed when the radioactive substance A has a hîgher radiation intensity. A l~rger receptacle is used as sho~m at 1' when the radiation intensity of the radioactive waste A' is less. In the case of higher intensity~ therefore, a greater thickness of the shielding material ~ is provided.
A tube lb may open into the receptacle, a correspond-ing tube lb' being provided in the case of the embodiment of FIG. 2, to fill the radioactive material into the inner recep-tacle. Alternatively, the tubes lb and lb' may be eliminated when the receptacle 1 or 1' is filled prior to its insertion into the outer recep-tacle 2.
As sh~wn in FIG. 1, the space 3 may also be provided ~
with heating rods 8 or other treating meansfor subjecting ~he ~`
radioactive wastes to evaporation or other -thermal treatment~
The hea~ing rods may also be used, if desired, to melt the shielding material 4 and ensure a complete distribut~on of the ~;shielding material 4 within the space 3 without air bubbles or the like. The heating rods 8 are lost within the body of the shielding 4 and become part of the package.
In the embodiment of FIGS. 1 and 2, the walls of ~he inner and outer receptacles are formed with rods 7 and 7' which project into the material 4 and serve to anchor the material ~f and the receptacle 1'.
The receptacle 1 and the receptacle 2 can be provided with passa~es 6 and 6' for venting the gases from the package during the E;lling or heating operations or to serve as filling passages. The tubes lb and lb' and the passages ~ and 6' are ultimately filled with radiation shielding material. ~ore particularly? the passages 6 can serve ~or pumping material into the package or evacuating vapors therefrom. A ~aterial capable ,~
~3 .
69~7~
of encapsulating the radioac~ive wastes and hardening insicle the tube, e.g. liquid bitumen, can also be introduced through the passages ~ in which case the liquid bitu~en can ultimately fill these passagesO
As can be seen from FIG. 4, the cover 10 for the outer receptacle 14 can be complementarily stepped at 12 to fit tightly upon the mouth 13 of the outer receptacle 14. In this caseeye 18 is affixed ko the outer receptacle 14 while bolts 1~ attached to plates 17 may be embedded in the concrete of the container 14 so that nuts 15 can be threaded onto the bolts 1~ to secure the cover 10 in place, An alternative construction has been shown in FI~. 5 in which the bolts lh receive nuts 19 which are also formed with necks 20 to which the e~es 21 are secured. In this case, the cover-securing means is also provided with lifting eyes to enable the package to be moved by a crane, In the e~bodiment of FIG. ~, the eye 22 is formed as a nut 23 on a bolt 24 swingable on a lug 25 about a pen 2~ anchored in the container 27 and within a slot 28 thereof. When the lug is swung in the counterclockwise sense into a slot 29 of the cover 30, the nut 23 may be tightened to clamp the cover in place.
In place of the heating rods 8, heating means such as tubes through which a heating fluid can be circulated, can be received in the chamber 3.
_9_
Claims (9)
1. A packaging system for the disposal of radioactive wastes of different radiation intensities, comprising:
an outer receptacle of a standard size uniform for all of said intensities and of a predetermined radiation absorbing capacity;
a plurality of inner receptacles of different volumes adapted to receive radioactive waste, a selected one of said inner receptacles being enclosed within said outer receptacle and having a volume determined by the intensity of the radi-ation emitted by the radioactive waste thereof with a smaller inner receptacle receiving waste of greater radiation intensity and a larger inner receptacle receiving waste of lesser radi-ation intensity;
spacer means for centering the selected inner recep-tacle within said outer receptacle so that the space between the outer receptacle and the selected inner receptacle is greater for the smaller inner receptacles than for the larger inner receptacles; and a radiation-shielding material disposed all around said selected inner receptacle in said space between the outer wall of said selected inner receptacle and the inner wall of said outer receptacle so that the thickness of the radiation-shielding material around the selected inner recep-tacle is greater for the smaller inner receptacles receiving waste of greater radiation intensity than for the larger inner receptacles receiving waste of lesser radiation intensity.
an outer receptacle of a standard size uniform for all of said intensities and of a predetermined radiation absorbing capacity;
a plurality of inner receptacles of different volumes adapted to receive radioactive waste, a selected one of said inner receptacles being enclosed within said outer receptacle and having a volume determined by the intensity of the radi-ation emitted by the radioactive waste thereof with a smaller inner receptacle receiving waste of greater radiation intensity and a larger inner receptacle receiving waste of lesser radi-ation intensity;
spacer means for centering the selected inner recep-tacle within said outer receptacle so that the space between the outer receptacle and the selected inner receptacle is greater for the smaller inner receptacles than for the larger inner receptacles; and a radiation-shielding material disposed all around said selected inner receptacle in said space between the outer wall of said selected inner receptacle and the inner wall of said outer receptacle so that the thickness of the radiation-shielding material around the selected inner recep-tacle is greater for the smaller inner receptacles receiving waste of greater radiation intensity than for the larger inner receptacles receiving waste of lesser radiation intensity.
2. The system defined in claim 1 wherein said spacer means includes spacer elements extending outwardly from the outer wall of each of said inner receptacles.
3. The system defined in claim 1, further comprising heating means in the space between said receptacles.
4. The system defined in claim 3 wherein said heating means are heating rods embedded in said radiation-shielding material.
5. The system defined in claim 1 wherein said outer receptacle is provided with a cover, further comprising means for securing said cover on said outer receptacle.
6. The system defined in claim 5 wherein said outer receptacle is composed of reinforced concrete.
7. The system defined in claim 6 wherein said inner receptacle has a cover.
8. The system defined in claim 7, further comprising at least one passage formed in said outer receptacle and communicating with said inner receptacle.
9. The system defined in claim 8 wherein said inner wall of said outer receptacle and said outer wall of said inner receptacle are provided with anchor elements embedded in said radiation-shielding material.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CA296,091A CA1096974A (en) | 1978-01-31 | 1978-01-31 | Device for the storage or disposal of radioactive wastes |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CA296,091A CA1096974A (en) | 1978-01-31 | 1978-01-31 | Device for the storage or disposal of radioactive wastes |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CA1096974A true CA1096974A (en) | 1981-03-03 |
Family
ID=4110673
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CA296,091A Expired CA1096974A (en) | 1978-01-31 | 1978-01-31 | Device for the storage or disposal of radioactive wastes |
Country Status (1)
| Country | Link |
|---|---|
| CA (1) | CA1096974A (en) |
-
1978
- 1978-01-31 CA CA296,091A patent/CA1096974A/en not_active Expired
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