CA1111579A - Nuclear reactor fuel channel - Google Patents
Nuclear reactor fuel channelInfo
- Publication number
- CA1111579A CA1111579A CA314,386A CA314386A CA1111579A CA 1111579 A CA1111579 A CA 1111579A CA 314386 A CA314386 A CA 314386A CA 1111579 A CA1111579 A CA 1111579A
- Authority
- CA
- Canada
- Prior art keywords
- reactor
- end fitting
- channel
- fuel
- outboard
- 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
Links
- 239000003758 nuclear fuel Substances 0.000 title claims description 7
- 239000000446 fuel Substances 0.000 claims abstract description 47
- 239000002826 coolant Substances 0.000 claims abstract description 19
- 238000007789 sealing Methods 0.000 claims description 8
- 230000006872 improvement Effects 0.000 claims description 2
- 239000012530 fluid Substances 0.000 claims 1
- 210000004894 snout Anatomy 0.000 claims 1
- XLYOFNOQVPJJNP-ZSJDYOACSA-N Heavy water Chemical compound [2H]O[2H] XLYOFNOQVPJJNP-ZSJDYOACSA-N 0.000 description 8
- 230000009467 reduction Effects 0.000 description 4
- 230000008901 benefit Effects 0.000 description 3
- 239000000463 material Substances 0.000 description 3
- 238000005086 pumping Methods 0.000 description 3
- 230000000875 corresponding effect Effects 0.000 description 2
- 230000003292 diminished effect Effects 0.000 description 2
- 102000007999 Nuclear Proteins Human genes 0.000 description 1
- 108010089610 Nuclear Proteins Proteins 0.000 description 1
- NMFHJNAPXOMSRX-PUPDPRJKSA-N [(1r)-3-(3,4-dimethoxyphenyl)-1-[3-(2-morpholin-4-ylethoxy)phenyl]propyl] (2s)-1-[(2s)-2-(3,4,5-trimethoxyphenyl)butanoyl]piperidine-2-carboxylate Chemical compound C([C@@H](OC(=O)[C@@H]1CCCCN1C(=O)[C@@H](CC)C=1C=C(OC)C(OC)=C(OC)C=1)C=1C=C(OCCN2CCOCC2)C=CC=1)CC1=CC=C(OC)C(OC)=C1 NMFHJNAPXOMSRX-PUPDPRJKSA-N 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 230000004907 flux Effects 0.000 description 1
- 238000009434 installation Methods 0.000 description 1
- 238000000034 method Methods 0.000 description 1
- 230000008569 process Effects 0.000 description 1
- 230000005855 radiation Effects 0.000 description 1
- 238000005096 rolling process Methods 0.000 description 1
- 125000006850 spacer group Chemical group 0.000 description 1
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
- G21C19/14—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel characterised by their adaptation for use with horizontal channels in the reactor core
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C1/00—Reactor types
- G21C1/04—Thermal reactors ; Epithermal reactors
- G21C1/06—Heterogeneous reactors, i.e. in which fuel and moderator are separated
- G21C1/14—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being substantially not pressurised, e.g. swimming-pool reactor
- G21C1/16—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being substantially not pressurised, e.g. swimming-pool reactor moderator and coolant being different or separated, e.g. sodium-graphite reactor, sodium-heavy water reactor or organic coolant-heavy water reactor
- G21C1/18—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being substantially not pressurised, e.g. swimming-pool reactor moderator and coolant being different or separated, e.g. sodium-graphite reactor, sodium-heavy water reactor or organic coolant-heavy water reactor coolant being pressurised
- G21C1/20—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being substantially not pressurised, e.g. swimming-pool reactor moderator and coolant being different or separated, e.g. sodium-graphite reactor, sodium-heavy water reactor or organic coolant-heavy water reactor coolant being pressurised moderator being liquid, e.g. pressure-tube reactor
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
Landscapes
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
ABSTRACT OF THE DISCLOSURE
The improved fuel channels for Candu type nuclear reactors are provided with pressure tubes sealed to the end fittings by rolled joints recessed into the end fittings, having fuel located in the channel by means of flow-through shield plugs locked in position by fuel latches. The coolant feeder con-nections are located just outboard of the end shields of the calandria vessel, with a channel closure just outboard of each connection point. The end fittings may extend past the feeder bank to allow the fuelling machine to latch on, for refuelling the channel. An alternative arrangement provides for termination of the fuel channel extensions adjacent the channel closure, with the fuelling machine having a correspondingly extended connector to reach through the feeder bank to the end fittings.
The improved fuel channels for Candu type nuclear reactors are provided with pressure tubes sealed to the end fittings by rolled joints recessed into the end fittings, having fuel located in the channel by means of flow-through shield plugs locked in position by fuel latches. The coolant feeder con-nections are located just outboard of the end shields of the calandria vessel, with a channel closure just outboard of each connection point. The end fittings may extend past the feeder bank to allow the fuelling machine to latch on, for refuelling the channel. An alternative arrangement provides for termination of the fuel channel extensions adjacent the channel closure, with the fuelling machine having a correspondingly extended connector to reach through the feeder bank to the end fittings.
Description
llilS7~ Case 2533 This invention is dirècted to a nuclear reactor assembly and in particular to an improved fuel channel.
In nuclear reactors of the pressure tube type having a plurality of fuel channels extending in sealed relation between a pair of opposed end shields of the calandria vessel, the cost of the reactor assembly is greatly affected by the amount of fuel in the channels and of the contained quantity of heavy water coolant.
Candu type reactors presently in service utilize pressure tube arrangements having the nuclear fuel extending partially within the calandria end shields, and also having the fuel latches within the end shield in direct contacting relation with the outermost fuel bundle. A rolled joint connecting the fuel channel with the end fitting is located within the end shield, inboard of the fuel latch, and closely adjacent the outermost fuel bundle. The end fitting body extends outwardly beyond the bank of coolant feeders, having a feeder connection located a considerable distance outboard of the end shield, and a channel closure member outboard thereof.
In accordance with the present invention a nuc-lear reactor is provided having a calandria with a plurality of fuel channels for operation with pressurized coolant and nuclear fuel therein, each channel being supported and located within a pair of opposed end shields, the channel comprising a tubular container mounted in aligned sealing relation with an end fitting body extending outwardly beyond the end shield, shield plug means within the channel, latch means to selectively retain the shield plug means within the reactor, the shield plug means extending from the latch means to the l~liS~9 case 2533 calandria side of the channel joint when in use, so as to position nuclear fuel substantially inboard of the end shields. The latch means for retaining the shield plug means and nuclear fuel within the fuel channel is located outboard of the calandria end shield, having the coolant feeder conduit connection with the end fitting body located closely adjacent and outboard of the end shield, with removable channel closure means located outboard of the feeder conduit within the end fitting body, the end fitting body including end fitting means to receive a refuelling machine in aligned sealing relation with the fuel channel.
In comparing the novel arrangement presented herewith with the known prior art, in addition to the advantage of substantially shielding the fuel channel rolled joint from irradiation, there are certain other important advantages:
1) for a given length of calandria pressure tube, the number of fuel bundles may be reduced, by the avoidance of having portions of a fuel bundle extending into the end fittings, within the end shield.
In nuclear reactors of the pressure tube type having a plurality of fuel channels extending in sealed relation between a pair of opposed end shields of the calandria vessel, the cost of the reactor assembly is greatly affected by the amount of fuel in the channels and of the contained quantity of heavy water coolant.
Candu type reactors presently in service utilize pressure tube arrangements having the nuclear fuel extending partially within the calandria end shields, and also having the fuel latches within the end shield in direct contacting relation with the outermost fuel bundle. A rolled joint connecting the fuel channel with the end fitting is located within the end shield, inboard of the fuel latch, and closely adjacent the outermost fuel bundle. The end fitting body extends outwardly beyond the bank of coolant feeders, having a feeder connection located a considerable distance outboard of the end shield, and a channel closure member outboard thereof.
In accordance with the present invention a nuc-lear reactor is provided having a calandria with a plurality of fuel channels for operation with pressurized coolant and nuclear fuel therein, each channel being supported and located within a pair of opposed end shields, the channel comprising a tubular container mounted in aligned sealing relation with an end fitting body extending outwardly beyond the end shield, shield plug means within the channel, latch means to selectively retain the shield plug means within the reactor, the shield plug means extending from the latch means to the l~liS~9 case 2533 calandria side of the channel joint when in use, so as to position nuclear fuel substantially inboard of the end shields. The latch means for retaining the shield plug means and nuclear fuel within the fuel channel is located outboard of the calandria end shield, having the coolant feeder conduit connection with the end fitting body located closely adjacent and outboard of the end shield, with removable channel closure means located outboard of the feeder conduit within the end fitting body, the end fitting body including end fitting means to receive a refuelling machine in aligned sealing relation with the fuel channel.
In comparing the novel arrangement presented herewith with the known prior art, in addition to the advantage of substantially shielding the fuel channel rolled joint from irradiation, there are certain other important advantages:
1) for a given length of calandria pressure tube, the number of fuel bundles may be reduced, by the avoidance of having portions of a fuel bundle extending into the end fittings, within the end shield.
2) the adoption of a flow-through shield plug in conjunction with a fuel latch located outside the end shield, in addition to increased latch accessibility, also reduces latch irradiation.
3) the location of the coolant feeder and the channel closure closely adjacent the end shield provides a significant reduction in the inventory of heavy water within the reactor, with cor-responding cost improvement.
4) the reduction in fuel channel flow passage ~ ~ Case 2533 length and the reduction in the number of fuel bundles within the channel significantly reduces the drop in pressure of coolant pumped along the channel, thereby reducing the pumping energy requirement.
5) the size and therefore the cost of pumps and motors to drive the pumps, is significantly and advantageously reduced.
A further, and quite unobvious advantage of the presently disclosed arrangement (which results from reduced irradiation of the rolled joint region) is that the rolled joint at one end of the channel can be made larger in diameter than the other channel end to permit removal and replacement of the pressure tube without the need to disturb the attachment of other components such as the end fittings. Thus, using a pressure tube having one end enlarged to a diameter providing radial clearance from the outside diameter (O.D.) of the tube main portion, upon severance of the tube rolled joints, located at the tube ends, the pressure tube can be withdrawn without disturbing the channel end fitting. It is only possible to replace the pressure tube without replacing the end fitting if the end fitting in the region of the rolled joint is not embrittled in prior service such that it would crack during the rolling operation. Since the end fitting is not removed during replacement of the pressure tube the feeder connection is not disturbed. The joint of the feeder connection is difficult to make and inspect for quality. Remaking of the tube rolled joint may be greatly facilitated by the provision of "spare" grooves in the end fitting into which the new tube end is rolled, upon retubing the calandria.
~ilS79 Case 2533 A further embodiment of this invention provides for termination of the fuel channel end fittings closely adjacent the feeder connection, and inboard of the feeder banks that run across the front of the reactor.
The reach of the refuelling machine is then extended, to clear the feeder bank. In this manner, the addition of an extension to the two fuelling machines serving the two faces of the reactor permits the diminishment of the length of the fuel channels for all the channels of the reactor by an equal length, with significant savings in material, and in the drainage requirements for retrieving heavy water during the daily uncoupling operation of the fuelling machine.
A further significant economy is that the end fitting section outboard of the closure plug can be of different material and manufactured by a different process from the inboard section, thus leading to economies in cost and material, by tailoring the irradiation and mechanical characteristics to the location requirements.
Certain embodiments of the invention are described, reference being made to the accompanying drawings, wherein:
Figure 1 is a prior art arrangement showing a diametrical cross-section of one end of a typical Candu reactor fuel channel;
Figure 2 is a like view of a first embodiment in accordance with the present invention, and Figure 3 is a like view illustrating further embodiments of the present invention.
Referring to Figure l the fuel channel lO
comprises a pressure tube 12 extending through the ~ ~ ~ ~ Case 2533 reactor core 14 and joined to the end fitting 18 and located in the end shield 16. The coolant feeder 20 is attached to the end fitting at the outboard end.
A closure 22 is also located at the outboard end of the channel 10. The end fitting body 18 is provided with a flange 19 by which a refuelling machine (not shown) can be attached in sealing relation with the fuel channel 10.
The pressure tube 12 is normally secured by a rolled joint 23 to the end fitting body 18 outside of the reactor core. A fuel latch 24 is located adjacent the joint 23 on the outboard side of the joint 23. The latch 24 locates the string of fuel 27 and permits selective passage of fuel bundles 27 along the channel 10 during refuelling. A shield plug 26 within the channel 10 reduces the outward passage of radiation emanating from the fuel bundles 27 through the end of the channel.
A liner 28 is provided within the end fitting to ensure free passage of coolant outside the shield plug.
In the first disclosed embodiment, Figure 2 shows a fuel channel 30 having a pressure tube 32 extending over the reactor core 14 and joined to end fitting 38 and located in the end shield 16. The rolled joint 43 between the end fitting body 38 and the pressure tube 32 is recessed into the end shield 16.
The end fitting body 38 is provided with an extension portion 39, the outboard end of wh~ch carries a flange 19 by which a refuelling machine tnot shown) can be attached in sealing relation with the fuel channel 30.
A fuel latch 24 within the end fitting body 38 is located well outboard of the rolled joint 43, the latch 24 being illustrated as located outboard (leftwardly) ~9 Case 2533 of the end shield 16.
An elongated flow-through shield plug 46 extends from the latch 24 to a position inboard of the joint 43, so as to position the outermost fuel bundle 27 within the reactor core 14 and inboard of the end shield 1~. A
liner is not required within the end fitting 38.
A coolant feeder 40 is located outboard of, and closely adjacent the fuel latch 24, with a closure 22 shown just outboard of the feeder 40. Coolant feeders 40' for adjacent fuel channels are arranged in a bank above the end fitting extension 39.
Comparing the embodiment of Figure 2 with the prior art arrangement of Figure 1, it can be seen that the joint 43 is located further outboard than the cor-responding joint 23 of the prior art, while the shield plug 46 positions the outermost fuel bundle 27 sensibly inboard of the end shield 16.
The relocated fuel has the effect of "saving"
one half bundle at each end of a pressure tube 30, thereby reducing by one the number of bundles within the channel 30, as compared to the channel 10, without producing any substantial diminution in neutron flux intensity within the calandria, and substantially without reduction in the effective mass of fuel in the core of the reactor.
Due to less fuel in the channel and the absence of the liner 28, the pressure drop in coolant flow, passing from the feeder at one end of the channel to the feeder at the remote end of the channel is correspondingly diminished, so that smaller pumps and pump motors may be utilized with commensurate savings, or, without changing to smaller sizes, a greater safety f~ctor is provided.
The significant potential savings also extend to the ~ ~ Case 2533 electrical energy requirement for pumping the coolant through the fuel channels which is correspondingly diminished. In a typical reactor installation a diminution in pumping requirement of about I0~ is ~on-templated.
In the case of the illustrated embodiment, for a Candu type reactor, the coolant is heavy water, and it is seen that the volume of coolant between incoming and outgoing feeders 40 is substantially reduced, compared with the prior art, by an amount approximately equal to the internal volume of the extension portion 39 of the end fitting body 38, i.e. outboard of the closure 22.
A further significant difference between the illustrated embodiment of Figure 2 and that of the prior art is the location of the fuel latch 24 outboard of the end shield 16, and having elongated shield plug 46 in interposed relation between the latch 24 and the outermost fuel bundle 27.
By locating the fuel latch 24 well outboard of the joint 43, in the case of rolled joints it is possible to size the components outboard of the joint 43 such that the joint 43 may be machined out and the pressure tube 32 withdrawn outwardly through the extension 39 with minimum extraneous work, and a replacement pressure tube 32 reinserted and sealed in position.
Referring to the Figure 3 embodiment, an additional or spare set of grooves 25, illustrated as being 3 in number, is provided, to facilitate retubing of the reactor. Furthermore, the end fitting body 18 is abreviated so as to terminate adjacent the feeder 40 and inboard of the feeders 40', thereby dispensing with 1~1~79 Case 2533 extension portions 39 for all of the fuel channels, which are compensated for by extending the length of the fuelling machine connection accordingly.
A spacer sleeve 28' facilitates coolant flow and the passage of fuel into and out of the reactor.
A further, and quite unobvious advantage of the presently disclosed arrangement (which results from reduced irradiation of the rolled joint region) is that the rolled joint at one end of the channel can be made larger in diameter than the other channel end to permit removal and replacement of the pressure tube without the need to disturb the attachment of other components such as the end fittings. Thus, using a pressure tube having one end enlarged to a diameter providing radial clearance from the outside diameter (O.D.) of the tube main portion, upon severance of the tube rolled joints, located at the tube ends, the pressure tube can be withdrawn without disturbing the channel end fitting. It is only possible to replace the pressure tube without replacing the end fitting if the end fitting in the region of the rolled joint is not embrittled in prior service such that it would crack during the rolling operation. Since the end fitting is not removed during replacement of the pressure tube the feeder connection is not disturbed. The joint of the feeder connection is difficult to make and inspect for quality. Remaking of the tube rolled joint may be greatly facilitated by the provision of "spare" grooves in the end fitting into which the new tube end is rolled, upon retubing the calandria.
~ilS79 Case 2533 A further embodiment of this invention provides for termination of the fuel channel end fittings closely adjacent the feeder connection, and inboard of the feeder banks that run across the front of the reactor.
The reach of the refuelling machine is then extended, to clear the feeder bank. In this manner, the addition of an extension to the two fuelling machines serving the two faces of the reactor permits the diminishment of the length of the fuel channels for all the channels of the reactor by an equal length, with significant savings in material, and in the drainage requirements for retrieving heavy water during the daily uncoupling operation of the fuelling machine.
A further significant economy is that the end fitting section outboard of the closure plug can be of different material and manufactured by a different process from the inboard section, thus leading to economies in cost and material, by tailoring the irradiation and mechanical characteristics to the location requirements.
Certain embodiments of the invention are described, reference being made to the accompanying drawings, wherein:
Figure 1 is a prior art arrangement showing a diametrical cross-section of one end of a typical Candu reactor fuel channel;
Figure 2 is a like view of a first embodiment in accordance with the present invention, and Figure 3 is a like view illustrating further embodiments of the present invention.
Referring to Figure l the fuel channel lO
comprises a pressure tube 12 extending through the ~ ~ ~ ~ Case 2533 reactor core 14 and joined to the end fitting 18 and located in the end shield 16. The coolant feeder 20 is attached to the end fitting at the outboard end.
A closure 22 is also located at the outboard end of the channel 10. The end fitting body 18 is provided with a flange 19 by which a refuelling machine (not shown) can be attached in sealing relation with the fuel channel 10.
The pressure tube 12 is normally secured by a rolled joint 23 to the end fitting body 18 outside of the reactor core. A fuel latch 24 is located adjacent the joint 23 on the outboard side of the joint 23. The latch 24 locates the string of fuel 27 and permits selective passage of fuel bundles 27 along the channel 10 during refuelling. A shield plug 26 within the channel 10 reduces the outward passage of radiation emanating from the fuel bundles 27 through the end of the channel.
A liner 28 is provided within the end fitting to ensure free passage of coolant outside the shield plug.
In the first disclosed embodiment, Figure 2 shows a fuel channel 30 having a pressure tube 32 extending over the reactor core 14 and joined to end fitting 38 and located in the end shield 16. The rolled joint 43 between the end fitting body 38 and the pressure tube 32 is recessed into the end shield 16.
The end fitting body 38 is provided with an extension portion 39, the outboard end of wh~ch carries a flange 19 by which a refuelling machine tnot shown) can be attached in sealing relation with the fuel channel 30.
A fuel latch 24 within the end fitting body 38 is located well outboard of the rolled joint 43, the latch 24 being illustrated as located outboard (leftwardly) ~9 Case 2533 of the end shield 16.
An elongated flow-through shield plug 46 extends from the latch 24 to a position inboard of the joint 43, so as to position the outermost fuel bundle 27 within the reactor core 14 and inboard of the end shield 1~. A
liner is not required within the end fitting 38.
A coolant feeder 40 is located outboard of, and closely adjacent the fuel latch 24, with a closure 22 shown just outboard of the feeder 40. Coolant feeders 40' for adjacent fuel channels are arranged in a bank above the end fitting extension 39.
Comparing the embodiment of Figure 2 with the prior art arrangement of Figure 1, it can be seen that the joint 43 is located further outboard than the cor-responding joint 23 of the prior art, while the shield plug 46 positions the outermost fuel bundle 27 sensibly inboard of the end shield 16.
The relocated fuel has the effect of "saving"
one half bundle at each end of a pressure tube 30, thereby reducing by one the number of bundles within the channel 30, as compared to the channel 10, without producing any substantial diminution in neutron flux intensity within the calandria, and substantially without reduction in the effective mass of fuel in the core of the reactor.
Due to less fuel in the channel and the absence of the liner 28, the pressure drop in coolant flow, passing from the feeder at one end of the channel to the feeder at the remote end of the channel is correspondingly diminished, so that smaller pumps and pump motors may be utilized with commensurate savings, or, without changing to smaller sizes, a greater safety f~ctor is provided.
The significant potential savings also extend to the ~ ~ Case 2533 electrical energy requirement for pumping the coolant through the fuel channels which is correspondingly diminished. In a typical reactor installation a diminution in pumping requirement of about I0~ is ~on-templated.
In the case of the illustrated embodiment, for a Candu type reactor, the coolant is heavy water, and it is seen that the volume of coolant between incoming and outgoing feeders 40 is substantially reduced, compared with the prior art, by an amount approximately equal to the internal volume of the extension portion 39 of the end fitting body 38, i.e. outboard of the closure 22.
A further significant difference between the illustrated embodiment of Figure 2 and that of the prior art is the location of the fuel latch 24 outboard of the end shield 16, and having elongated shield plug 46 in interposed relation between the latch 24 and the outermost fuel bundle 27.
By locating the fuel latch 24 well outboard of the joint 43, in the case of rolled joints it is possible to size the components outboard of the joint 43 such that the joint 43 may be machined out and the pressure tube 32 withdrawn outwardly through the extension 39 with minimum extraneous work, and a replacement pressure tube 32 reinserted and sealed in position.
Referring to the Figure 3 embodiment, an additional or spare set of grooves 25, illustrated as being 3 in number, is provided, to facilitate retubing of the reactor. Furthermore, the end fitting body 18 is abreviated so as to terminate adjacent the feeder 40 and inboard of the feeders 40', thereby dispensing with 1~1~79 Case 2533 extension portions 39 for all of the fuel channels, which are compensated for by extending the length of the fuelling machine connection accordingly.
A spacer sleeve 28' facilitates coolant flow and the passage of fuel into and out of the reactor.
Claims (11)
1. In a nuclear reactor having a core located in a calandria with a plurality of pressurized fuel channels extend-ing in a core space between opposed end shields bounding the calandria, each channel comprising a tubular container having each end thereof secured by a joint in fluid pressure sealing re-lation with an end fitting located in the respective end shield, having an end fitting body extending outwardly beyond the end shield, the improvement comprising: shield plug means within said channel, latch means located in the channel to releasably secure the plug means therein, said plug means extending within the end shield, when in use to position nuclear fuel within the core space of the reactor.
2. The reactor as claimed in claim 1, said joint comprising a rolled joint, said latch means being located within said end fitting body at a distance outboard of said rolled joint.
3. The reactor as claimed in claim 2 having a coolant feeder conduit connected with said end fitting body at a position closely adjacent and outboard of said end shield.
4. The reactor as claimed in claim 3 having a fuel channel closure means in removable sealing relation within said end fitting body and located close to the end shield.
5. The reactor as claimed in claim 4 said end fitting body extending in an outboard direction beyond said closure means, having end fitting means at the outboard end thereof to receive a refuelling machine in sealing relation therewith.
6. The reactor as claimed in claim 1, said shield plug means comprising a flow-through plug having passages for coolant in free flowing relation therethrough.
7. The reactor as claimed in claim 1, said end fitting having an inner diameter providing a radial clearance from the outer diameter of said tubular container, along a major portion of the length thereof, to permit withdrawal of said tubular portion outwardly through the end fitting.
8. The reactor as claimed in claim 7, said tubular container having an end portion of enlarged diameter to facilitate joining thereof to said end fitting by forming said joint as a rolled joint.
9. The reactor as claimed in claim 4, claim 7 or claim 8, said end fitting body terminating outboard of said end shield and inboard of a plurality of feeder conduits connected to adjacent said channels.
10. The reactor as claimed in claim 5, said end fitting body comprising a first portion extending outboard of said closure means and a second portion joined thereto and extending inboard of said closure means.
11. The reactor as claimed in claim 5, in combination with a refuelling machine, said machine having an extended snout portion for sealing attachment to said end fitting means, said end fitting means being abbreviated to terminate adjacent a coolant feeder connected with the end fitting means.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CA314,386A CA1111579A (en) | 1978-10-26 | 1978-10-26 | Nuclear reactor fuel channel |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CA314,386A CA1111579A (en) | 1978-10-26 | 1978-10-26 | Nuclear reactor fuel channel |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CA1111579A true CA1111579A (en) | 1981-10-27 |
Family
ID=4112706
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CA314,386A Expired CA1111579A (en) | 1978-10-26 | 1978-10-26 | Nuclear reactor fuel channel |
Country Status (1)
| Country | Link |
|---|---|
| CA (1) | CA1111579A (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US9418765B2 (en) | 2013-03-14 | 2016-08-16 | Roger Ian LOUNSBURY | Nuclear reactor cores comprising a plurality of fuel elements, and fuel elements for use therein |
-
1978
- 1978-10-26 CA CA314,386A patent/CA1111579A/en not_active Expired
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US9418765B2 (en) | 2013-03-14 | 2016-08-16 | Roger Ian LOUNSBURY | Nuclear reactor cores comprising a plurality of fuel elements, and fuel elements for use therein |
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