WO1999026254A1 - Crayon de combustible nucleaire - Google Patents
Crayon de combustible nucleaire Download PDFInfo
- Publication number
- WO1999026254A1 WO1999026254A1 PCT/FR1998/002350 FR9802350W WO9926254A1 WO 1999026254 A1 WO1999026254 A1 WO 1999026254A1 FR 9802350 W FR9802350 W FR 9802350W WO 9926254 A1 WO9926254 A1 WO 9926254A1
- Authority
- WO
- WIPO (PCT)
- Prior art keywords
- fuel rod
- capsule
- sheath
- fuel
- rod according
- Prior art date
Links
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
- G21C3/02—Fuel elements
- G21C3/04—Constructional details
- G21C3/16—Details of the construction within the casing
-
- 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
Definitions
- the invention relates to a fuel rod of a nuclear fuel assembly of a water-cooled nuclear reactor and in particular of a pressurized water-cooled nuclear reactor
- Nuclear reactors cooled by water and in particular nuclear reactors cooled by pressurized water comprise a core constituted by fuel assemblies juxtaposed and made so that the cooling water of the circulating nuclear reactor ensures the removal of heat produced by nuclear reaction inside fuel assemblies
- Nuclear fuel assemblies are generally formed in the form of bundles of cylindrical rods of great length arranged and maintained in a framework, in an arrangement such that the axes of the pencils are parallel to each other
- the fuel rods themselves consist of a cylindrical tubular sheath made of a weakly neutron absorbing material such as a zirconium alloy, a plurality of pellets of nuclear combustible material, such as uranium oxide UO 2 or mixed uranium and plutonium oxide stacked one on the other in the axial direction of the sheath, so as to constitute a column of combustible pellets, sealing plugs at the ends of the sheath, and a retaining spring interposed between one end of the column of fuel pellets and the internal surface of one of the plugs
- the inside of the sheath filled with the fuel pellets is filled with '' a neutral gas under pressure such as helium
- the plugs are tightly fixed to the filling gas, so that the filling gas of the sheath remains confined inside the pencil after s its manufacture and throughout the use of the pencil inside the nuclear reactor core
- the pressurized gas filling the pencil sheath coming into contact with the fuel pellets makes it possible
- fission gas gaseous form
- a solution to this problem could consist in reducing the initial pressure of the filling gas in the sheath, but this solution is generally not acceptable since a high pressure of the filling gas is necessary to obtain a good thermal transfer between the pellets. and the cladding and good mechanical stability of the cladding at the start of irradiation
- the object of the invention is therefore to propose a nuclear fuel rod comprising a tubular cladding, a plurality of pellets of nuclear combustible material stacked in the form of a column pastilles of fuel, in the axial direction inside the sheath, a closure plug at each of the ends of the sheath, a means of axial retention of the column interposed between the internal surface of one of the plugs and one of the ends of the column of fuel pellets and a pressurized gas filling the sheath which is closed in a sealed manner to the filling gas by the plugs, the fuel rod being produced so as to limit the pressure of the gas at the end life of the fuel rod.
- the fuel rod further comprises a capsule contained inside the sheath closed in a sealed manner and delimiting a chamber whose internal pressure is lower than the pressure of the gas contained in the sheath of the pencil, part of which at the less is deformable and / or destructible at a predetermined pressure of the gas contained in the sheath.
- Figure 1A is a sectional view of the lower part of a fuel rod according to the invention comprising a capsule according to a first embodiment.
- Figure 1B is a sectional view of the upper part of a fuel rod according to the invention comprising a capsule according to the first embodiment equipped with a gas flow damping disc.
- FIGS. 2A and 2B show a part of the wall of the capsule of the pencil shown in FIG. 1 produced in the form of a rupture disc according to a first alternative embodiment.
- Figure 2A is a sectional view through a diametrical plane of the rupture disc.
- Figure 2B is a top view of the rupture disc along B of Figure 2A.
- FIGS. 3A and 3B show a part of the wall of the capsule of the fuel rod shown in FIG. 1, produced in the form of a rupture disc according to a second variant embodiment.
- Figure 3A is a sectional view through a diametrical plane of the rupture disc.
- Figure 3B is a top view along B of Figure 3A.
- FIGS. 4A and 4B show a rupture disc according to a third alternative embodiment.
- Figure 4A is a sectional view through a diametrical plane of the rupture disc.
- Figure 4B is a top view along B of Figure 4A.
- FIGS. 5A and 5B show a rupture disc according to a fourth embodiment.
- Figure 5A is a sectional view through a diametrical plane of the rupture disc.
- Figure 5B is a top view along B of Figure 5A.
- Figure 6 is an axial sectional view of a capsule of a fuel rod according to the invention and according to a second embodiment.
- Figure 7 is a sectional view along 7-7 of Figure 6.
- Figure 8 is an axial sectional view of a capsule of a fuel rod according to the invention and according to a third embodiment.
- Figure 9 is a sectional view along 9-9 of Figure 8.
- Figure 10 is a sectional view of the upper part of a fuel rod according to the invention comprising a capsule according to the second embodiment.
- FIG. 11 is a sectional view of the upper part of a fuel rod according to the invention comprising a capsule according to the second embodiment and according to an alternative embodiment.
- FIG. 1A we see the lower part of a fuel rod of an assembly of a pressurized water nuclear reactor generally designated by the reference 1
- the fuel rod 1 comprises a generally tubular sheath 2 of cylindrical shape made of a metallic material which absorbs weakly the neutrons such as a zirconium alloy
- the sheath 2 of the fuel rod has a diameter of the order of 10 mm and a length greater than 4 m
- the sheath 2 is closed at its ends by metal plugs such as the plug 3 visible in FIG. 1
- the fuel assemblies are placed inside the nuclear reactor core in a vertical position, so that the fuel rods of the assembly are placed with their axis in the vertical direction.
- the lower part of the pencil 1 that is to say the part of the pencil placed lowest when the pencil is placed in a fuel assembly
- the sheath 2 of the rod 1 contains a plurality of pellets of combustible material 4 of cylindrical shape with circular section whose diameter is slightly less than the internal diameter of the sheath 2, at least when the fuel rod is new or has only undergone limited irradiation
- the fuel pellets 4 are stacked one on the other so as to constitute a column of combustible pellets or fissile column having as an axis the axis of the sheath 2 of the pencil. Because the diameter of the pellets 4 of combustible material is smaller than the inner diameter of the sheath 2, there remains a slight radial clearance between each of the pellets and the inner surface of the sheath 2
- a free space is left between the upper end of the column of fuel pellets and the inner surface of the upper cap of the rod.
- a helical spring or other holding device is inserted between the inner surface of the upper cap of the pencil and the upper end of the column of fuel pellets 4
- a wedge can be placed over part of the length of the free space, between the column of pellets and the cap
- the free space between the upper end of the fuel pellet column and the inner surface of the upper cap constitutes a manifold filled with pressurized helium.
- the fuel pellets 4 undergo swelling and radial expansion, so that the radial clearance between the pellets 4 and the cladding 2 of the fuel rod gradually decreases and ends up cancel each other for a certain rate of irradiation of the combustible material of the pellets 4
- the fission reactions caused by the neutron bombardment of the fissile material of the fuel pellets 4, in the core of the reactor cause the formation of fission gases which mix with the pressurized helium filling the pencil sheath.
- the pressure inside the cladding increases and can become prohibitive after a certain period of use and depending on the operating conditions of the rod in the core of the nuclear reactor.
- the fuel rod 1 comprises, in its lower part shown in FIG. 1, a capsule 5 comprising a wall fully closed in a leaktight manner delimiting a chamber 6 whose internal pressure is lower than the pressure of the filling gas of the sheath 2 of the fuel rod 1.
- the chamber 6 of the capsule 5 is filled with helium at a low pressure, for example with helium at atmospheric pressure.
- the wall of the capsule 5 delimiting the sealed chamber 6 is constituted by a tube 7 whose diameter is less than the inner diameter of the sheath 2 and by two lids 8 and 9 fixed in sealed manner by welding to the ends of the tube 7.
- the tube 7 and the lids 8 and 9 are made of metal such as an austenitic stainless steel or a zirconium alloy which may be identical to the zirconium alloy constituting the cladding 2 and the caps of the nuclear fuel rod.
- the cover 8 of the capsule 5 constitutes a rupture disc capable of rupturing and of bringing the internal volume of the sheath into communication with the chamber 6, when the pressure of the gas contained in the sheath 2 of the fuel rod exceeds a certain predetermined limit. There is thus obtained a reduction in the pressure inside the sheath, by increasing the volume of expansion of the pressurized gas at the end of the fuel rod life.
- the capsule 5 can be fixed in a coaxial arrangement to the sheath 2, in the lower part of the fuel rod 1, as it is visible in FIG. 1A.
- a support tube 10 is engaged and fixed on an internal part of the plug 3 with reduced diameter.
- the tube 10 is fixed in a leaktight manner on the plug 3, for example by means of welding points produced after engagement of the tube 10 on the reduced diameter end portion of the plug 3.
- the cover 8 of the capsule 5 formed in the form of a rupture disc is fixed by welding to the upper end part of the support tube 10.
- the assembly operations of the capsule and the plug 3 are carried out before the plug is placed in the lower part of the sheath 2 of the pencil and before the sheath is filled with the fuel pellets.
- the plug 3 has a blind opening 11 in an axial direction opening onto the internal surface of the plug and passing through the reduced diameter portion of the plug 3 on which the support tube 10 is engaged.
- the tube 10 and the plug 3 are drilled engaged one on the other in a diametrical direction so as to obtain a channel 12 opening onto the outer surface of the support tube 10 and passing through the blind hole
- the internal part of the support tube 10 is placed in communication and in equipression with the annular space reserved between the internal surface of the sheath 2 of the pencil and the external surface of the capsule 5 constituting the lower collector of the pencil.
- the capsule 5 can also be located in the upper part of the pencil, as it is visible in FIG. 1 B.
- Figure 1B there is shown the upper part of a fuel rod in which is disposed a capsule 5 'similar to the capsule 5 described above and shown in Figure 1A.
- FIGS. 1A and 1B have the same references, the elements represented in FIG. 1B and located in the upper part of a pencil being however assigned the sign '(prime).
- the sheath 2 of the rod 1 is closed by a plug 3 'constituting the upper plug of the fuel rod.
- the capsule 5 ' is fixed under the plug 3' by means of a support tube 10 '.
- the hole 11 ′ is extended by a hole of small diameter 1 opening out onto the upper surface of the plug 3 ′ which is used for the introduction of the filling gas into the sheath.
- the hole 11 'a is then sealed.
- a rupture disc 8 ' closes the capsule at its upper part at the end of the support tube 10'.
- a disc 24 pierced with a small central opening is fixed in a transverse arrangement so as to separate the chamber 6 ′ from the capsule 5 ′ into two parts.
- the communication between the annular space of the rod between the sheath and the capsule and the part of the chamber 6 ′ in which the expansion of the gas takes place is carried out by means of the opening of the disc 24.
- a large pressure drop is thus obtained on the flow of the gas contained in the sheath of the pencil, during the rupture of the disc 8 '.
- the helical spring 25 holding the column of fuel pellets 4 is interposed between the upper end of the column of pellets and the bottom of the capsule 5 '.
- the rupture disc is subjected, on its external face, to the pressure of the gas contained in the sheath of the pencil and, on its internal face, to the internal pressure of the chamber 6 or 6 ′ and therefore to the pressure differential between the gas contained in the pencil and the 6 or 6 'sealed chamber of the 5 or 5' capsule
- the rupture disc closing the chamber of the capsule at its lower part consists of a metal disc 28, for example made of zirconium alloy one of the flat faces of which has a circular groove 13 the depth of which corresponds to a fraction of the total thickness of the metal disc 28 A weakened zone of reduced thickness is thus formed in a peripheral part of the rupture disc
- the meridian section of the toric groove 13 has the shape of a U with rounded angles. This avoids a concentration of stresses in the bottom of the groove which would occur if the groove had a cross-section. V shape
- the groove 13 is preferably produced on the upper face of the bursting disc 28 which is directed towards the inside of the chamber 6 of the hood.
- the groove of the bursting disc is thus completely separated from the gas mixture containing fission gases contained inside the sheath of the rod placed in the operating reactor In this way, the tendency to stress corrosion (CSC) of the rupture disc is limited, when the fuel rod is placed in the core of the reaction vessel.
- CSC stress corrosion
- FIGS. 3A and 3B a second alternative embodiment of the rupture disc 28 has been shown, which is constituted, in this case, by a metal disc on one of the plane faces from which two grooves 14 and 14 ′ are machined in the direction diametral making between them a certain angle which is preferably equal to 90 °
- the bottom of the grooves 14 and 14 ′ which are produced for example using a grinding wheel in the form of a pre- feels a shape in an arc of a circle and the grooves have an increasing depth in the direction going from the periphery towards the central part of the disc 28.
- the grooves 14 and 14 ′ are preferably produced on the upper face of the disc 28 which is directed towards the interior of the chamber of the capsule. Because the part of the disc comprising the grooves is isolated from the gas mixture containing fission gases contained in the cladding, the stress corrosion of the rupture disc is limited when the fuel rod is in the core of the nuclear reactor.
- the rupture disc 28 has a weakened zone along which rupture of the disc occurs when the pressure of the gas contained in the cladding of the fuel rod exceeds a predetermined value.
- the adjustment of the residual thickness of the disc 28 at the level of the groove 13, in order to calibrate the rupture disc is obtained by making a groove 13 d 'a perfectly determined depth.
- the residual thickness of the rupture disc 28 in its central part where the residual thickness is the smallest can be perfectly determined using a tool, for example a disc-shaped grinding wheel with a well-defined diameter to make a groove of a perfectly determined length L.
- the rupture disc can be calibrated very precisely, so as to obtain the rupture of the disc and the communication of the capsule chamber with the internal volume of the pencil sheath, for a pressure of the gas contained in the sheath perfectly determined.
- FIGS. 4A and 4B it is also possible to produce, by machining the rupture disc, a circular cup 22 and coaxial with the disc, the bottom of which has a thickness less than the thickness of the edge of the disc which does not is not machined. In this case, the rupture of the disc occurs along the bottom of the bowl 22 and the residual thickness of the disc defining the level of rupture is the thickness of the bottom of the bowl. As shown in FIGS.
- the cover 28 ′ of the capsule can be produced in the form of a spherical cap, the central part of the convex surface of which has been machined to form a flat surface 23.
- a flat surface 23 for example by grinding or polishing, obtaining a flat with a perfectly defined diameter makes it possible to fix the residual thickness of the cover 28 ', in its central part, at a precise predetermined value and therefore perform a precise calibration of the cover 28 ′, because the radius of the spherical cap is defined with very good precision.
- a rupture disc of uniform thickness that is to say without zone of reduced thickness.
- the metallurgical structure of the disc can be locally weakened or strengthened, for example by local heat treatment or by softening or hardening additions.
- zirconium alloy disc for example Zircaloy 4
- a locally hardened and annealed disc in its central part by heating with a laser beam. It is thus possible to recrystallize part of the disc or to operate a transformation in ⁇ phase of the alloy. It is also possible to introduce locally into the disc softening additions (Sn, Cd) in solid solution, or hardeners (Cr, Fe, C, O).
- the operation of the capsule is adjusted to trigger the increase in the expansion volume of the fuel rod, so that the triggering, by rupture of the disc, is produce at the start of the closing of the clearance between the pellets 4 and the sheath 2, due to the swelling under irradiation of the fuel pellets 4
- the pressurized gas contained in the upper collector of the fuel rod between the upper end of the pillar column and the inner surface of the upper plug can flow into the lower collector and into the capsule chamber, at the time of rupture of the disc, without causing the formation of a shock wave which could occur due to the very large pressure difference between the internal volume of the sheath and the capsule chamber.
- the rupture pressure of the cover is generally between 90 and 150 bars and fixed at a value which depends on the control mode of the nuclear reactor.
- the fuel rod according to the invention has, after rupture of the cover constituting a part of the wall of the capsule, an increased expansion volume and therefore a reduced pressure of the gas filling the sheath of the fuel rod. The duration is thus increased. life of the fuel rod
- FIGS. 6 and 7 has shown a capsule, in the case of a second embodiment of the pencil, generally designated by the reference 15 which is intended to be placed inside the sheath of a pencil of fuel between the lower end of the column of fuel pellets and the inner surface of the lower cap of the rod to allow a variation in the volume of expansion of the fission gases, inside the sheath, at the end of the life of the fuel rod.
- the capsule 15 is constituted by an openwork tube 16 in which are made slots 17 of axial direction passing through the wall of the tube, a metal membrane 18 disposed inside the openwork tube and two closure plates 19a and 19b fixed by welding to the ends of the perforated tube 16 on which the ends of the membrane 18 disposed coaxially inside the perforated tube 16 are also fixed by welding, in leaktight manner.
- the wall of the tube 16 is crossed by eight slots 17 equidistant from axial direction.
- the membrane 18 has a lateral surface formed by successive facets connected together along edges of the membrane in the axial direction and having, in cross section, as can be seen in FIG. 7, a slight curvature, the convex face of the facets being directed towards the outside of the membrane.
- This outwardly convex curvature makes it possible to obtain a bracing effect when the membrane is subjected to the external pressure of the filling fluid of the pencil sheath.
- the membrane has a cross section having substantially the shape of a polygon whose sides have a slight convex curvature directed towards the outside. In the embodiment shown in Figures 6 and 7, the membrane 18 has eight facets of identical dimensions.
- the capsule 15 is placed inside a fuel tube in an arrangement coaxial with the sheath of the tube, that is to say with its axis 20 placed along the axis of the fuel rod.
- the column of fuel pellets is supported on the upper closing plate 19b and the lower closing plate 19a comes to bear on the inner surface of the lower plug of the fuel rod.
- the membrane 18 which is tightly fixed on the closure plates 19a and 19b at its ends delimits, at its internal part, a chamber 21 totally isolated from the interior volume of the sheath of the fuel rod.
- the chamber 21 can be filled with a gas such as helium at a pressure substantially lower than the filling pressure of the fuel rod cladding and for example a pressure close to atmospheric pressure.
- the membrane 18 is therefore subjected to compression forces under the effect of the pressure of the gas contained in the fuel rod.
- the membrane 18 has a thickness and mechanical characteristics such that it can deform by buckling, from a predetermined pressure level inside the fuel rod cladding When the pressure inside the fuel rod cladding exceeds the value causing buckling deformation, the membrane is ruptured In this way, in a first, the volume of expansion of the gas inside the fuel rod cladding increases due to the deformation of the membrane and, in a second step, this volume increases suddenly by rupture of the membrane.
- the curved facets p have a cross section having a flattened sinusoid shape or, possibly, a circular arc shape to optimize the conditions of deformation and rupture of the membrane at perfectly determined pressure levels
- the membrane is calculated so as to begin to deform by buckling under the effect of the pressure increase due to the fission gases, at the beginning of the closing of the clearance between the pellets and the sheath of the fuel rod under the effect of the irradiation undergone by the pellets in the core of the nuclear reactor and to undergo a rupture and a total destruction at the moment when the fuel pellets come into contact with the inner surface of the fuel rod cladding with high contact pressure.
- a capsule is preferably used, the membrane of which deforms by buckling at a pressure between 90 and 150 bars for a temperature of the order of 350 ° C.
- the perforated tube and the closure plates of the capsule are made of stainless steel.
- the membrane is made of a metal whose mechanical characteristics are adapted to the operating conditions of the capsule with regard to the pressure and temperature of deformation and rupture of the membrane.
- the membrane has a thickness between 0J 0 and 0.45 mm and generally a thickness close to 0.20 mm.
- the perforated tube 16 supports the weight of the column of fuel pellets, the compression force of the spring holding the fuel pellets and the bottom effect induced by the external pressure on the closure plates of the chamber 21 of the capsule.
- the perforated tube 16 is subjected to the axial direction forces indicated above, to which is added the compression force induced by the deformation of the membrane by buckling.
- This limit pressure is reached at the start of the closing of the clearance between the pellets and the internal surface of the fuel rod cladding.
- the membrane undergoes a total rupture, so that the perforated tube no longer undergoes the compressive force imposed by the membrane.
- the perforated tube is then capable of withstanding the compression force in the axial direction produced by the contact with high pressure between the fuel pellets and the tube.
- FIGS. 8 and 9 there is shown a capsule according to the invention and according to a third embodiment, constituting a variant of the embodiment shown in Figures 6 and 7.
- the corresponding elements in Figures 6 and 7 of on the one hand and in FIGS. 8 and 9 on the other hand have the same references with, however, the exponent '(prime) for the elements of the capsule 15' shown in FIGS. 8 and 9.
- the capsule 15 'shown in Figures 8 and 9 are identical to the operating principle and the structure of the capsule 15 described above. However, unlike the capsule 15, the capsule 15 'has an external tube 16' crossed by two bores 17 'of diametrically opposite radial direction in its middle part, instead of an external perforated tube crossed by eight slots 17 of axial direction.
- the membrane 18 'and the closing plates 19'a and 19'b of the capsule 15' are identical, respectively, to the membrane 18 and to the closing plates 19a and 19b, of the capsule 15.
- the device according to the invention therefore makes it possible to adjust the volume of expansion of the gas in the fuel rod as a function of the irradiation of the fuel pellets and to limit the pressure of the gas contained in the sheath of the pencil, at the end of the life of the fuel rod.
- the device also makes it possible to withstand the forces due to pressure contact between the pellets and the fuel rod cladding.
- the device according to the invention makes it possible to increase the lifetime and the rate of irradiation of a fuel rod inside the core of a nuclear reactor.
- the capsule can have a wall whose shape is different from the shapes which have been described above.
- the rupture zone of the wall, for a well defined pressure inside the pencil sheath, can be obtained by means different from those which have been described.
- the capsule can be placed inside the fuel rod, in a different zone from the lower part of the rod and interposed between elements different from the lower end of the column of fuel pellets and the lower cap.
- the capsule can be placed for example under the upper cap of the pencil, as it can be seen in Figure 10.
- the lower part of the capsule 26 includes an expansion chamber 27 separated from the capsule 26 'by a disc 29 through which a small central opening.
- the pressurized gas contained in the sheath of the pencil passes into the expansion chamber 27 through the opening of the disc 29.
- the holding spring 25 fuel pellets 4 is interposed between the lower bottom of the capsule 26 and the upper end of the column of fuel pellets 4. It is also possible, as can be seen in FIG.
- the capsule 26 can be fixed, as previously described, under the plug 3 ', so that it is placed inside the spring 25'.
- a means for holding the column of pellets constituted by a clip in this case, the capsule can be placed above the clip.
- the capsule can be free and placed directly or by means of a support on the column of pellets.
- the capsule has a length such that the volume of fuel pellets cannot come to bear on the plug via the capsule, when they expand in service.
- the invention applies to any fuel rod of a water-cooled nuclear reactor comprising a cladding closed by plugs and a column of fuel pellets disposed inside the cladding.
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- 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
Description
Claims
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
EP98954507A EP1032939A1 (fr) | 1997-11-19 | 1998-11-03 | Crayon de combustible nucleaire |
Applications Claiming Priority (2)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
FR97/14511 | 1997-11-19 | ||
FR9714511A FR2771211B1 (fr) | 1997-11-19 | 1997-11-19 | Crayon de combustible nucleaire |
Publications (1)
Publication Number | Publication Date |
---|---|
WO1999026254A1 true WO1999026254A1 (fr) | 1999-05-27 |
Family
ID=9513536
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
PCT/FR1998/002350 WO1999026254A1 (fr) | 1997-11-19 | 1998-11-03 | Crayon de combustible nucleaire |
Country Status (3)
Country | Link |
---|---|
EP (1) | EP1032939A1 (fr) |
FR (1) | FR2771211B1 (fr) |
WO (1) | WO1999026254A1 (fr) |
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN109935361A (zh) * | 2017-12-19 | 2019-06-25 | 中国原子能科学研究院 | 一种方形双面冷却环形燃料组件 |
Citations (7)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
FR2113998A1 (fr) * | 1970-11-17 | 1972-06-30 | Kernforschung Gmbh Ges Fuer | |
FR2172276A1 (fr) * | 1972-02-16 | 1973-09-28 | Westinghouse Electric Corp | |
DE2633352A1 (de) * | 1976-07-24 | 1978-01-26 | Interatom | Brenn-, brut- oder absorberstab mit ueberdrucksicherung |
JPS5311295A (en) * | 1976-07-16 | 1978-02-01 | Mitsubishi Electric Corp | Fuel rod for nuclear reactor |
JPS54125387A (en) * | 1978-03-24 | 1979-09-28 | Hitachi Ltd | Penetration structure for nuclear reactor container |
US4596690A (en) * | 1983-12-21 | 1986-06-24 | The United States Of America As Represented By The United States Department Of Energy | Fission gas release restrictor for breached fuel rod |
JPH09113662A (ja) * | 1995-10-23 | 1997-05-02 | Hitachi Ltd | 原子力燃料集合体の燃料棒 |
-
1997
- 1997-11-19 FR FR9714511A patent/FR2771211B1/fr not_active Expired - Fee Related
-
1998
- 1998-11-03 WO PCT/FR1998/002350 patent/WO1999026254A1/fr not_active Application Discontinuation
- 1998-11-03 EP EP98954507A patent/EP1032939A1/fr not_active Withdrawn
Patent Citations (7)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
FR2113998A1 (fr) * | 1970-11-17 | 1972-06-30 | Kernforschung Gmbh Ges Fuer | |
FR2172276A1 (fr) * | 1972-02-16 | 1973-09-28 | Westinghouse Electric Corp | |
JPS5311295A (en) * | 1976-07-16 | 1978-02-01 | Mitsubishi Electric Corp | Fuel rod for nuclear reactor |
DE2633352A1 (de) * | 1976-07-24 | 1978-01-26 | Interatom | Brenn-, brut- oder absorberstab mit ueberdrucksicherung |
JPS54125387A (en) * | 1978-03-24 | 1979-09-28 | Hitachi Ltd | Penetration structure for nuclear reactor container |
US4596690A (en) * | 1983-12-21 | 1986-06-24 | The United States Of America As Represented By The United States Department Of Energy | Fission gas release restrictor for breached fuel rod |
JPH09113662A (ja) * | 1995-10-23 | 1997-05-02 | Hitachi Ltd | 原子力燃料集合体の燃料棒 |
Non-Patent Citations (3)
Title |
---|
PATENT ABSTRACTS OF JAPAN vol. 002, no. 050 (M - 015) 10 April 1978 (1978-04-10) * |
PATENT ABSTRACTS OF JAPAN vol. 003, no. 148 (M - 083) 7 December 1979 (1979-12-07) * |
PATENT ABSTRACTS OF JAPAN vol. 097, no. 009 30 September 1997 (1997-09-30) * |
Cited By (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN109935361A (zh) * | 2017-12-19 | 2019-06-25 | 中国原子能科学研究院 | 一种方形双面冷却环形燃料组件 |
CN109935361B (zh) * | 2017-12-19 | 2024-05-31 | 中国原子能科学研究院 | 一种方形双面冷却环形燃料组件 |
Also Published As
Publication number | Publication date |
---|---|
EP1032939A1 (fr) | 2000-09-06 |
FR2771211A1 (fr) | 1999-05-21 |
FR2771211B1 (fr) | 2000-01-28 |
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