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Sommaire du brevet 1167176 

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  • lorsque la demande peut être examinée par le public;
  • lorsque le brevet est émis (délivrance).
(12) Brevet: (11) CA 1167176
(21) Numéro de la demande: 1167176
(54) Titre français: FAISCEAU COMBUSTIBLE TORSADE
(54) Titre anglais: FUEL BUNDLE WITH SKEWED ELEMENTS
Statut: Durée expirée - après l'octroi
Données bibliographiques
(51) Classification internationale des brevets (CIB):
  • G21C 3/18 (2006.01)
  • G21C 3/04 (2006.01)
  • G21C 3/22 (2006.01)
  • G21C 3/32 (2006.01)
(72) Inventeurs :
  • BARNS, GEORGE M. (Canada)
(73) Titulaires :
  • CANADIAN GENERAL ELECTRIC COMPANY LIMITED
(71) Demandeurs :
  • CANADIAN GENERAL ELECTRIC COMPANY LIMITED (Canada)
(74) Agent: RAYMOND A. ECKERSLEYECKERSLEY, RAYMOND A.
(74) Co-agent:
(45) Délivré: 1984-05-08
(22) Date de dépôt: 1981-10-09
Licence disponible: S.O.
Cédé au domaine public: S.O.
(25) Langue des documents déposés: Anglais

Traité de coopération en matière de brevets (PCT): Non

(30) Données de priorité de la demande: S.O.

Abrégés

Abrégé anglais


CASE 774
FUEL BUNDLE WITH SKEWED ELEMENTS
ABSTRACT OF THE DISCLOSURE
A nuclear reactor having elongated pressure tube
fuel channels containing rodded fuel elements assembled
as discreate bundles arranged in end to end serial
relation within the pressure tube, for the passage of
liquid coolant therepast is provided with improved fuel
bundles having the rodded elements skewed with respect
to the pressure tube in order to promote swirling
of the liquid or liquid and vapour mixture coolant in its
passage along the fuel channel. In addition to the evident
rotational effect due to the "twist", the effect of
skewing the fuel rods in each bundle is to create a
progressive change in flow area distribution between the
interior subchannels and the subchannels surrounding the
bundle, from both ends of each fuel bundle to its
longitudinal centre, tending to promote uniform heating
of the liquid or liquid and vapour coolant by flow
deflection between the interior subchannels and the
surrounding subchannels.

Revendications

Note : Les revendications sont présentées dans la langue officielle dans laquelle elles ont été soumises.


CASE-277
- 7 -
The embodiments of the invention in which an
exclusive property or privilege is claimed are defined
as follows:
1. In a nuclear reactor having pressurized fuel
channels containing liquid coolant and a plurality of
fuel bundles arranged in abutting serial relation,
each fuel bundle having a plurality of cylindrical rods
extending in attached relation between spaced end
plates, arranged in at least one ring about the bundle
axis the improvement comprising said rods extending
in skewed relation between said end plates, to provide
a plurality of interconnected coolant flow channels,
wherein said coolant flow channels vary in their
respective flow sections, progressively along the length
of said bundle.
2. The nuclear fuel bundle as claimed in Claim 1
having an outer row of said rods and at least one inner
row of said rods the angle inclination of said inner
row rods being less than the angle of inclination of
said outer row rods.
3. The nuclear fuel bundle as claimed in Claim 1
having flat end plates of constant thickness, each
said ring of rods having the length of the respective
rods compensated according to the respective angle of
skew, such that welded attachment to said end plates is
provided at both ends of all said rods.
4. The nuclear fuel bundle as claimed in Claim 1
at least one said end plate having raised annular rings
therein to receive said rods in welded relation thereto.
5. The bundle as claimed in Claim 1, Claim 2 or
Claim 3, an outer ring of said rods being inclined at
a predetermined angle such that said end plates are in
effect rotated from each other by an angle in the range
10° to 40°.

Case 2774
- 8 -
6. The bundle as claimed in Claim 1, claim 2 or
Claim 3 in combination with a nuclear fuel reactor, said
reactor having appropriate coolant circulation pumping
capability, in order to promote circulation of said
liquid coolant past said bundles.
7. The bundle as claimed in Claim 4 in combination
with a nuclear fuel reactor, said reactor having appropriate
coolant circulation pumping capability, in order to
promote circulation of said liquid coolant past said
bundles.

Description

Note : Les descriptions sont présentées dans la langue officielle dans laquelle elles ont été soumises.


I ~ B'~
CASE-277~
-- 1 --
FUEL BUNDLE WITX S:KEWED ELEM~NTS
This invention is directed to nuclear reactors, and
to fuel for use in nuclear reactors, and methods of
manufacturing such nuclear fuel.
In the Canadian Deuterium Uranium (acronym CANDU)
type of reactor, use is made of fuel channels arranged within
a calandria, somewhat in the manner of a boiler. The
fuel channels each comprises a tube containing pressuriæed
liquid and a so-called string of fuel bundles arranged
in serial, end-to-end relation extending substantially
the full length of the individual channel. Each fuel
bundle has a plurality of clad fuel rods or elements, as
many as but not limited to 37 rods per bundle each rod
being about one half inch in diameter by about twenty
inches long, being arranged in concentric rings and
supported by welding of the rod end caps to a pair of
spaced-apart end plates, with the polar axis of each
rod being parallel with the bundle main axis and the end
plates perpendicular to the bundle main axis.
In the CANDU type reactor the coolant is maintained
usuall~ in liquid phase with a small proportion of
vapour at the exit end of some channels, being pressurized
in order to raise the maximum coolant temperature, the
coolant liquid being deuterium-oxide i.e./ heavy water.
` One of the problems encountered is the matter of
controlling coolant flow in a suitable condition to
.. ,
.. ~ .... . .
.: .
. ~ .
.
.

I ~ 6 7~ 7~;
CASE-2774
-- 2 --
effect required heat transfer from the individual fuel
rods to the liquid coolant. In accordance with prior
art and practice, the ~uel rods extend parallel with
the tube main axis, thereby ensuring minimal coolant
pressure drop along the length of the fuel channel,
to thereby minimize pumping requirement for the reactor.
In accordance with the present invention a nuclear
reactor is provided having rodded fuel bundles wherein
each bundle comprises a pluralit:y of fuel rods having
the ends thereof secured to opposed end plates, the rods
being skewed at angles in the typical range oE 0.3 to
0.5, but not restricted to this range, from an axis
parallel with the principal axis of the bundle. A
centre rod lying on the bundle axis remains parallel to
the bundle axis and the end plates perpendicular to the
bundle axis.
One method by which the present invention may be
practiced is to assemble the fuel rods and end plates,
prior to final securement~ in a rectilinear axially
aligned condition, and then rotate one of the end plates
about its polar axis by a desired angle of displacement,
in the typical range of 10 to ~0, but not restricted
to this range from the other plate as to generate symmetrical
skewing of all of the fuel rods. It will be understood
that this method will produce differential axial skewing
between respective rings of rods, with the radially outer
ring of fuel rods being skewed at the greatest angle,
and radially inner rings being progressively less skewed.
The effect of skewing is to shorten the projected
length or distance between the ends of the fuel rods
measured parallel to the bundle axis, but because of the
differentiated skew angles, the outer ring of rods is
shortened more than inner rings, which are progressively
shortened by reduced amounts. A centre rod on the bundle
a~is being not skewed maintains a projected length
equal to its actual length.`

IJ~'~t 7~
CASE-2774
-- 3
A tabulated analysis given below in Table 1, shows
the decreases in rod projected length resulting from
varying degrees of skew, arrived at by respective
relative rotations of the end plates. This length
variation, according to the ring, can be compensated
by appropriately increasing the fuel rod lengths, or
by providing compensating annular steps or lands on the
end plate.
One effect steming from the skewed construction is
that the fuel bundle takes on a slightly waisted appearance,
i.e., the bundle diameter diminishes progressively from
a maximum value at the ends to a minimum value at the
longitudinal mid point.
This has the effect of causing the interconnected
coolant flow channels which exist in the in-terior of the
fuel bundle, and those exterior to the bundle, to change
in their relative cross sectional areas, thereby tending
to cause a coolant transfer during coolant flow along
the bundle from within the bundle to the outside of the
bundle, and vice versa. This is complementary to the
rotatory effect on coolant flow due to the handling
effect of rod skewing (i.e~, twist).
Certain embodiments of the invention are described,
reference being made to the accompanying drawings,
wherein;
Figure 1 is a side view of a fuel bundle according
to the present invention.
Figure 2 and Figure 3 are end views taken at 2-2
and 3-3 of Figure 1.
Figure 4 is a diametrical sectioned view of an end
plate taken on line 4-4, a bundle having all rods of
uniform length.
For illustratory purposes, a bundle having 37 rods
is shown,arranged as three concentric rings of rods
about a single rod lying on the bundle axis.

I ~ 6 ~ :? ~ ~;
CA5E-2774
-- 4 --
Referring to the drawings, the bundle 20 is the
same as a normal rectilinear bundle, but having a 40
counter clockwise twist applied between the ends
thereof. Thus, in the illustratad embodiment, the
respective rod positions for the rods 22 are displaced
by two intervals in the case of the numbered, radially
outer ring of rods, as shown in Figures 2 and 3.
The Figure 4 sectioned view is somewhat schematic,
in that perforations of the end plate 24, which permit
through-flow to assist coolant circulation~ have not
been illustrated, to better show the provision of
annular lands 26, 28 and 30 for the respective three
annular rows of rods 22 contained in the bundle. The
differences in the heights of the annular lands 26,
28 and 30 exaggerated for purposes of illustration,
compensate for the differential axial shortening
taking place in the equal length rods of the respective
rings of rods, due to the different angles in inclination,
as set forth below in Table I, with corresponding
differences in effective axial length, as measured
between the bundle end plates. Alternatively, a flat
end plate of constant thickness, withou-t the annular
lands 26, 28 and 30, may be used with rods having
lengths that are increased to compensate for the
differential axial shortening taking place due to the
different angles of inclination in the respective rings
as set forth in Table I.

- J ;1 ~;7 ~ 7~i
.
_ 5 _ CASE 2774
TABLE 1
SOME RELEVANT DIMENSIONS FOR THE ILLUSTRATED
EMBODIMENT OF A 37-ROD BUNDLE
Mid Length ¦ Mid Length Pitch
Subchannel Area Circle Diam. Decrease
End~ Change - inche.s
Plate
Rotary ___________________________ _ _ ______~_~
Angle Exterior Interior Outer Mid Inner
Channels Channels Ring Ring Ring
_~ .
00 O O o O O
10 +3.3 -2.1 .0133 .0086 .0046
20 -~12.7 -8.1 .0518 .0344 .0178
30 +28.3 -18.0 .1162 .0771 .0399
40 +49 -31.5 .2056 .1365 .0707
_______ _
_ ~ __ _~
End Rod Angle to Flow Porjected Axial RodLen9th
Plate Change - inches
Rotatory _ _ ~ _ _ ___~
Angle outer Mid Inner Outer Mid Inner
_ Ring Ring Ring Ring Ring Ring
O O O O O O
10 0.9 0.6 0.3 .0023 .0010 .0003
20 1.8 1.2 0.6 .0091 .0040 .0011
30 2.6 1.7 0.9 .0201 ~ .0089 .0024
40 3.5 2.3 1.2 .0351 .0155 .0041
:
__ ~ ~. __
~' .
:'

'7 ~
C~SE-277
~ 6 --
Referring to Table I, in the case of the 40
rotatory angle between the end plates, there is a
projected rod length change, as measured axially between
the end plates of the fuel bund:Le, amounting to
approximately 35 thousandths of an inch ("thou."), in the
case of the radially outer ring of rods, 15 thousandths
of an inch in the case of the m:id ring of rods, and the
4 thousand-ths of an inch in the case of the inner ring
of rods. These are the lengths by which the rods in the
respective rings must be increased for the use of end
plates without steps.
In the case where rods of uniform length are used
throughout the bundle, both end plates 24 are approximately
stepped, to compensate ~or axial projected length
differences, the stepped differentials of the annular
rings or lands 26, 28 and 30 would be halved to values
of 17.5 thou., 7.5 thou., and 2 thou., approximately.
In the other three tabulated cases of a fuel bundle
having a lesser angle of skew, the axial distance
differentials are correspondingly reduced, to the extend
that, for a ten degree skew (Table I) the difference to
be made up at each'end would not exceed 1.15 thou., which
could be accommodated in the welding of the rod end cap
to the plate 24.

Dessin représentatif

Désolé, le dessin représentatif concernant le document de brevet no 1167176 est introuvable.

États administratifs

2024-08-01 : Dans le cadre de la transition vers les Brevets de nouvelle génération (BNG), la base de données sur les brevets canadiens (BDBC) contient désormais un Historique d'événement plus détaillé, qui reproduit le Journal des événements de notre nouvelle solution interne.

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Pour une meilleure compréhension de l'état de la demande ou brevet qui figure sur cette page, la rubrique Mise en garde , et les descriptions de Brevet , Historique d'événement , Taxes périodiques et Historique des paiements devraient être consultées.

Historique d'événement

Description Date
Inactive : CIB de MCD 2006-03-11
Inactive : Périmé (brevet sous l'ancienne loi) date de péremption possible la plus tardive 2001-05-08
Accordé par délivrance 1984-05-08

Historique d'abandonnement

Il n'y a pas d'historique d'abandonnement

Titulaires au dossier

Les titulaires actuels et antérieures au dossier sont affichés en ordre alphabétique.

Titulaires actuels au dossier
CANADIAN GENERAL ELECTRIC COMPANY LIMITED
Titulaires antérieures au dossier
GEORGE M. BARNS
Les propriétaires antérieurs qui ne figurent pas dans la liste des « Propriétaires au dossier » apparaîtront dans d'autres documents au dossier.
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Description du
Document 
Date
(aaaa-mm-jj) 
Nombre de pages   Taille de l'image (Ko) 
Dessins 1993-12-02 1 39
Page couverture 1993-12-02 1 15
Revendications 1993-12-02 2 54
Abrégé 1993-12-02 1 32
Description 1993-12-02 6 211