GB2104435A - Cylindrical vessels - Google Patents

Cylindrical vessels Download PDF

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Publication number
GB2104435A
GB2104435A GB08222383A GB8222383A GB2104435A GB 2104435 A GB2104435 A GB 2104435A GB 08222383 A GB08222383 A GB 08222383A GB 8222383 A GB8222383 A GB 8222383A GB 2104435 A GB2104435 A GB 2104435A
Authority
GB
United Kingdom
Prior art keywords
vessel
plates
radius
overlaying
cylindrical
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.)
Withdrawn
Application number
GB08222383A
Inventor
Alan Thomas Hooper
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.)
UK Atomic Energy Authority
Original Assignee
UK Atomic Energy Authority
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
Application filed by UK Atomic Energy Authority filed Critical UK Atomic Energy Authority
Priority to GB08222383A priority Critical patent/GB2104435A/en
Publication of GB2104435A publication Critical patent/GB2104435A/en
Withdrawn legal-status Critical Current

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Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21FPROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F5/00Transportable or portable shielded containers
    • G21F5/005Containers for solid radioactive wastes, e.g. for ultimate disposal
    • G21F5/008Containers for fuel elements

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  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Filling Or Discharging Of Gas Storage Vessels (AREA)

Abstract

A cylindrical vessel, suitable for use as a flask for storing and transporting radioactive material, is formed by overlaying similar curved plates (13) contained within the confines of inner and outer tubes (16, 17) which define the inner and outer walls of the vessel. Ductile material defining voidages, such as by perforations or profiling, may be included between the plates to reduce risk of impact damage and avoid the need for a separate impact limiting device. <IMAGE>

Description

SPECIFICATION Cylindrical vessels This invention relates to cylindrical vessels.
The invention is primarily concerned with the problem of providing massive cylindrical vessels for use as "flasks" for storing and transporting radioactive materials. To give an indication of one typical requirement, a steel flask suitable for a single light water reactor fuel element must have a bore of 45 cms and an outside diameter of about 110 cms, that is a wall thickness of about 32 cms. Such dimensions lead one to consider using constructional techniques already known for the manufacture of naval gun barrels but this poses technical problems and is expensive.
A cylindrical vessel according to the present invention is formed by overlaying similar curved plates each of which extends from the nominal inner wall of the vessel to the nominal outer wall of the vessel.
The plates are preferably of a common uniform thickness and formed by a rolling technique and are located between inner and outer tubes forming the vessel walls. When the vessel is required for storing and transporting radioactive material some impact limiting device will generally be required. To provide any known impact limiting device (which device itself has also to be of large dimensions) has the practical result that the vessel is reduced substantially in size as the overall size of a vessel and impact limiting device has restrictions imposed by rail or road gauge limitations.
Also in accordance with the present invention, ductile material, such as aluminium, or lead, is introduced between at least some of the overlaying curved plates which form the vessel, said material defining voidages into which the material can flow under impact on the vessel The material may be of sheet form with perforations to define voidages. Alternatively it could be of profiled form, such as ribbed.
Typically the material could occupy 30% of the wall volume of the vessel and have 20 to 50% voidage.
The fact that voidage exists and the fact that the ductile material (if taken to be aluminium) has a lower shielding capacity than the construction material of the curved plates (taken to be steel) will result in some increase in size of the vessel but this increase will not be so large as that created if any known impact limiting device were fitted: Where the vessel walls are defined by inner and outer tubes, their construction should be thin so as not to contribute too much stiffness under impact conditions. The voidage in the ductile material need not be uniformly dispersed. For example it is preferred that the voidage decreases as one approaches the inner tube of the vessel. Similarly the inner tube of the vessel should be thicker than the outer tube of the vessel.
Under impact sufficient to deflect any of the overlaying curved plates, ductile material is forced to flow into its voids. As the voilds fill so the resistance to further flow is increased.
The invention will now be described further with reference to the accompanying drawings in which: Figure 1 is- a diagrammatic half elevation illustrating construction; and Figure 2 is a similar elevation but on a much reduced scale to illustrate slopes.
A cylindrical vessel 10- (axis horizontal) having- a bore 11 and an outer surface 12 is formed by overlaying similar curved plates 13 of common uniform thickness. The plates may be tack-welded at 14 and 15so that they are held in their correct location.
The vessel 10 is itself located between inner and outer tubes 16, 17 which are supported by and sealed with end closures.
The drawing shows an idealised vessel with the plates 13 in contact. In practice, and to accommodate energy absorbing ductile material, the plates are spaced apart over most of their area. To illustrate this point, the idealised vessel 10 has thirtyfour plates each of 2.54 cms thickness without spaces between the plates. A practical vessel 10 would typically have thirty-two plates with a minimum gap of about 2 mm between the plates and larger gaps where energy absorbing material is used.
The drawing also illustrates the parameters used in the calculations of the curvatures of the plates 13.
The curve of the plates 13 is an involute- with: R cos A r where A = local angle (measured in radions) between the radius of the vessel and the tangent to the curve at that station.
R = base circle radius r = station radius B A-A, where B = angle between radius, where r = R and station radius.
where p = local radius of curvature of vane at radius r C = Angle between local tangent to vane and radius where r = R Knowing the base radius R and choosing a succession of values for C the curve of the vanes can be plotted from x = R (cosC + C sinC) y = R (sinc - C cosC) The base circle does not have to be the same diameter as the bore of the tube and there are some advantages in having it smaller, because the radius of vane curvature becomes very small as the vane approaches the base circle.
When a vessel as above described is used for radioactive material storage or transport it is seen that the curvature of the plates acts to avoid the presence of straight line paths in a radial sense along which nuclear "shine" can occur. There are straight line paths in the longitudinal sense but any shine along these paths can be dealt with at the end closures.
Assembly of the vessel 10 can take place from the ends of the vessels or by constructing two halves and assembling them together as shown on Figure 2.
The aforementioned construction described provides a degree of mechanical interiock protection for individual plates against impact loads. This is illustrated by consideration of Figure 2 in which the interlocking shape of a half vessel is indicated by hatching lines.

Claims (4)

1. A cylindrical vessel formed by overlaying similar curved plates each of which extends from the nominal inner wall of the vessel to the nominal outer wall of the vessel.
2. A vessel as claimed in claim 1 in which the plates are of a common uniform thickness.
3. A vessel as claimed in claim 1 or 2 in which a ductile material is introduced between at least some of the curved plates, said material defining voidages into which the material can flow under impact on the vessel.
4. A cylindrical vessel substantially as described with reference to the drawings.
GB08222383A 1981-08-10 1982-08-03 Cylindrical vessels Withdrawn GB2104435A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
GB08222383A GB2104435A (en) 1981-08-10 1982-08-03 Cylindrical vessels

Applications Claiming Priority (3)

Application Number Priority Date Filing Date Title
GB8124359 1981-08-10
GB8208744 1982-03-25
GB08222383A GB2104435A (en) 1981-08-10 1982-08-03 Cylindrical vessels

Publications (1)

Publication Number Publication Date
GB2104435A true GB2104435A (en) 1983-03-09

Family

ID=27261253

Family Applications (1)

Application Number Title Priority Date Filing Date
GB08222383A Withdrawn GB2104435A (en) 1981-08-10 1982-08-03 Cylindrical vessels

Country Status (1)

Country Link
GB (1) GB2104435A (en)

Cited By (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US6064710A (en) * 1997-05-19 2000-05-16 Singh; Krishna P. Apparatus suitable for transporting and storing nuclear fuel rods and methods for using the apparatus
WO2005041210A1 (en) * 2003-10-27 2005-05-06 Rossiisky Federalny Jaderny Tsentr - Vserossiisky Nauchno-Issledovatelsky Institut Tekhnicheskoi Fiziki Im. Akad. E.I. Zababakhina (Rfyats - Vniitf) Container for transporting and/or storing waste nuclear fuel
US7994380B2 (en) 2006-10-11 2011-08-09 Holtec International, Inc. Apparatus for transporting and/or storing radioactive materials having a jacket adapted to facilitate thermosiphon fluid flow
US8995604B2 (en) 2009-11-05 2015-03-31 Holtec International, Inc. System, method and apparatus for providing additional radiation shielding to high level radioactive materials

Cited By (7)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US6064710A (en) * 1997-05-19 2000-05-16 Singh; Krishna P. Apparatus suitable for transporting and storing nuclear fuel rods and methods for using the apparatus
WO2005041210A1 (en) * 2003-10-27 2005-05-06 Rossiisky Federalny Jaderny Tsentr - Vserossiisky Nauchno-Issledovatelsky Institut Tekhnicheskoi Fiziki Im. Akad. E.I. Zababakhina (Rfyats - Vniitf) Container for transporting and/or storing waste nuclear fuel
US7994380B2 (en) 2006-10-11 2011-08-09 Holtec International, Inc. Apparatus for transporting and/or storing radioactive materials having a jacket adapted to facilitate thermosiphon fluid flow
US8067659B2 (en) 2006-10-11 2011-11-29 Holtec International, Inc. Method of removing radioactive materials from a submerged state and/or preparing spent nuclear fuel for dry storage
US8415521B2 (en) 2006-10-11 2013-04-09 Holtec International, Inc. Apparatus for providing additional radiation shielding to a container holding radioactive materials, and method of using the same to handle and/or process radioactive materials
US8995604B2 (en) 2009-11-05 2015-03-31 Holtec International, Inc. System, method and apparatus for providing additional radiation shielding to high level radioactive materials
US9208914B2 (en) 2009-11-05 2015-12-08 Holtec International System, method and apparatus for providing additional radiation shielding to high level radioactive materials

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WAP Application withdrawn, taken to be withdrawn or refused ** after publication under section 16(1)