EP1166277A1 - Systeme de commande pour reacteur et procede approprie - Google Patents

Systeme de commande pour reacteur et procede approprie

Info

Publication number
EP1166277A1
EP1166277A1 EP00925052A EP00925052A EP1166277A1 EP 1166277 A1 EP1166277 A1 EP 1166277A1 EP 00925052 A EP00925052 A EP 00925052A EP 00925052 A EP00925052 A EP 00925052A EP 1166277 A1 EP1166277 A1 EP 1166277A1
Authority
EP
European Patent Office
Prior art keywords
neutron
bodies
reactor
neutron absorption
absorbing
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Withdrawn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
EP00925052A
Other languages
German (de)
English (en)
Inventor
Stephan Struth
Mario Kuhlmann
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.)
Forschungszentrum Juelich GmbH
Original Assignee
Forschungszentrum Juelich GmbH
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 Forschungszentrum Juelich GmbH filed Critical Forschungszentrum Juelich GmbH
Publication of EP1166277A1 publication Critical patent/EP1166277A1/fr
Withdrawn legal-status Critical Current

Links

Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C7/00—Control of nuclear reaction
    • G21C7/06—Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section
    • G21C7/08—Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section by displacement of solid control elements, e.g. control rods
    • G21C7/10—Construction of control elements
    • G21C7/107—Control elements adapted for pebble-bed reactors
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C7/00—Control of nuclear reaction
    • G21C7/28—Control of nuclear reaction by displacement of the reflector or parts thereof
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C9/00—Emergency protection arrangements structurally associated with the reactor, e.g. safety valves provided with pressure equalisation devices
    • G21C9/02—Means for effecting very rapid reduction of the reactivity factor under fault conditions, e.g. reactor fuse; Control elements having arrangements activated in an emergency
    • G21C9/027—Means for effecting very rapid reduction of the reactivity factor under fault conditions, e.g. reactor fuse; Control elements having arrangements activated in an emergency by fast movement of a solid, e.g. pebbles
    • 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 present invention relates to a method and a control system for regulating and selectively shutting down the power of a nuclear reactor. It also relates to a nuclear reactor including such a control system and to a neutron absorption body for regulating and optionally switching off the power of a nuclear reactor.
  • Today's nuclear fission reactors comprise a reactor core that contains nuclear fuel elements.
  • the nuclear fuel elements include the nuclear fuel (uranium, thorium and / or plutonium isotopes) and a moderator.
  • Nuclear fission releases fast neutrons, which are slowed down by the moderator in order to achieve an energy level that is suitable for causing another fuel core to fission. This in turn leads to the release of fast neutrons and heat, which is used to generate energy.
  • shutdown systems for nuclear reactors. They serve to end the nuclear chain reaction. At least one of these systems can also be used to regulate the operation, ie the power and the power profile of the reactor.
  • the shutdown systems conventionally operate by introducing neutron absorbing materials into the core or its surroundings (eg the surrounding reflector). The amount of such absorbers to be introduced must be sufficient to ensure a sufficiently fast control and, if necessary, to ensure a sufficient switch-off effect, for example in all operating and fault situations in the event of a temperature change and / or after a disintegration of
  • a shutdown system is also used for control purposes, these absorbers are not moved completely out of their effective positions during normal operation, so that the reactivity can be increased when extended further, i.e. the splitting rate can be increased.
  • a switch-off function is achieved by moving additional absorbers into effective positions, which stops the chain reaction.
  • HTR high temperature reactor
  • a characteristic of the pebble bed reactor is that new spherical fuel elements are introduced into its core during operation and old ones can be withdrawn from it if necessary.
  • Rods are usually used in the shutdown and control systems, in which the absorbent material is enclosed in metallic tubes. If the ball cluster core is designed accordingly, it is sufficient to insert such rods into the rod openings provided in the side reflectors. In addition, it is only possible for shutdown purposes to enclose the absorber in small balls instead of rods, as was the case with the second shutdown system of the MODUL-HTR concept. Such balls have become known as "Small Absorber Beads" (KLAKs). These KLAKs consist of graphite balls that contain boron or boron carbide. The KLAKs are placed in vertical so-called KLAK openings or bores.
  • KLAKs are less sensitive to temperature than metallic rods.
  • KLAKs collect by gravitation at the lower end of each KLAK channel and have to be filled up by gravitation or to reach higher levels be subtracted down from there to reduce the absorption level.
  • absorber materials have hitherto been used primarily in the form of the aforementioned rods in order to influence the performance profile and in particular the thermal performance profile in the desired manner in a controlled manner, usually in order to smooth such a profile.
  • HTR too, this is mainly done to avoid high local radiation exposure in the graphite reflector.
  • the concentration of spent fuel increases downwards.
  • the maximum power is usually in the upper half of the core.
  • the course of this maximum power in the upper half and thus also the resulting profile or the production of fast neutrons can be smoothed if the part of the absorber body of the control system that is used for power control, under normal operating conditions near this position, has maximum effect the top half. Extending from this position of maximum effect releases reactivity, while the introduction of more absorber material reduces this activity and ultimately leads to a shutdown.
  • the control system is generally designed for operation with bars. So far, KLAKs have only been used for the second shutdown system, ie only for complete shutdown. However, a recent South African patent application 98/0128 proposes a system in which KLAKs are also used to regulate the reactor power and the power profile.
  • the conventional control rods were each in the form of a rod, around which annular control bodies made of neutron-absorbing material such as boron carbide, hafnium carbide or the like were arranged.
  • annular control bodies made of neutron-absorbing material such as boron carbide, hafnium carbide or the like were arranged.
  • boron carbide is stable at temperatures up to at least 1600 ° C
  • the metal of the inner rod loses its required tensile strength at temperatures above 650 ° C. This causes problems because, for very good reasons, it was customary to arrange these metal rods hanging at the top in order to be able to lower them by gravitation into the core area and thus to slow down the chain reaction by increasing the neutron absorption and optionally to stop it entirely.
  • the neutron flow is highest in the upper areas of the reactor core, because fresh fuel element balls are conventionally introduced into the reactor core from above, while completely or partially used or spent fuel balls are withdrawn from the lower area. Accordingly, the level of the neutron flux in the reactor core decreases from top to bottom. It therefore makes sense that a control system is advantageous that primarily reaches the core area from above.
  • temperatures of around 900 ° C have become the norm during normal operation, and in the event of malfunctions, the temperatures of the absorber bodies can rise to over 1200 ° C, which far exceeds the tolerance limits of the metal rods.
  • a first aspect of the invention is a method for regulating and selectively shutting down the power of a nuclear reactor by one or more
  • Neutron absorption body or partial body which are movably accommodated in a cavity or cavities in the active area of the reactor, wherein in addition to the one or more neutron absorption bodies or partial bodies in the cavity or the cavities, one or more further bodies or partial bodies with properties of weakly neutrons absorbing to non-absorbing until Neutrons are housed in a reflective manner and said bodies or partial bodies and further bodies or partial bodies are moved in relation to one another and / or to the reactor core in order to control a neutron flow provided by the core by setting conditions which range from maximum neutron absorption to minimum neutron absorption or maximum neutron reflection .
  • Both types of bodies or partial bodies can be rotated in relation to one another. Both types of bodies or partial bodies can be moved as integrated units. Both can be combined into a single integral body or bodies.
  • the method may be a method of regulating and optionally shutting down a nuclear reactor to the extent that one or more neutron absorbing bodies are exposed to a neutron flux generated by the core of the reactor to absorb neutrons, and may be carried out with a neutron absorbing body which is one Neutron absorption surface area and a further surface area that is less neutron absorbing to non-absorbing and / or reflecting neutrons.
  • the degree of neutron absorption or non-absorption and / or neutron reflection can then be controlled by controlling the orientation of the absorbent body relative to the reactor core between an extreme orientation for maximum absorption at which the neutron sorbent surface area is maximally exposed to the neutron flux, and another extreme orientation for minimal or no neutron absorption and / or for neutron reflection, in which the weaker neutron absorbing or non-absorbing or reflecting area is so exposed.
  • the method of the invention can be carried out with a neutron absorption body, the orientation of which is controlled by its rotational movement between the two extreme orientations.
  • the cavity or cavities in the active area of the reactor can be open to the reactor core, and an area or areas of the bodies can be directly exposed to the reactor core.
  • open areas in the form of a slot or a sequence of slots or openings can be provided parallel to the axis of the reactor core.
  • the slots can then connect between the core region and the cavity or cavities and be dimensioned such that the neutron absorption body (s) are / are retained in the cavity or cavities in the channel, while fuel balls in the case of a pebble bed reactor are prevented from entering the cavity or to enter the cavities.
  • the neutron absorption body (s) can be located on a slope in order to automatically move into an orientation for maximum neutron absorption by gravitation in the event of an energy interruption or other malfunction.
  • the bevel can be designed, for example, as an inclined spiral plane, as a screw thread, as a worm or the like in cooperation with a suitable additional contact surface. be educated. In this way, the neutron absorption body can be held at the upper end of the inclined spiral plane during normal operation of the reactor. In such an embodiment, the body is automatically released at the upper end of the inclined spiral plane in the event of a power failure. The body then moves down the plane, rotating to automatically align for maximum neutron absorption.
  • the orientation of the absorption body (s) and possibly other bodies can be controlled by means which are actuated from outside the pressure body of the reactor.
  • a control system for regulating and optionally switching off the power of a nuclear reactor, including one or more neutron absorption bodies or partial bodies which are movably accommodated in a cavity or cavities in the active region of the reactor and in relation to one another and / or can be moved to the reactor core to control the neutron flux available from the core through setting conditions ranging from maximum neutron absorption to minimum neutron absorption and / or neutron reflection.
  • the invention extends to a nuclear reactor including a control system as described above.
  • the reactor can be a high temperature reactor (HTR), for example a pebble bed reactor.
  • HTR high temperature reactor
  • a neutron absorption body is provided for regulating and optionally switching off the power of a nuclear reactor, which has a neutron-absorbing surface area and in which a further surface area is weakly absorbing or non-absorbing or reflecting neutrons.
  • the neutron absorbing and weaker neutron absorbing or non-absorbing surface areas can be axially displaced in relation to each other.
  • the non-absorbent surface area can be neutrons reflective.
  • the neutron absorption body can be rod-shaped.
  • graphite blocks or stones are provided which are suitable for being assembled into a reactor reflector and for forming the cavity or cavities for the neutron absorption bodies with the above-described new features.
  • the graphite blocks or stones can be shaped and dimensioned such that they can be assembled into a reactor reflector in which cavities are formed which are open to the reactor core as described above.
  • the invention is preferably applied to reactors of the high temperature reactor (HTR) type and in particular to reactors in which fresh nuclear fuel with or without recirculated partially burned fuel is to be supplied at one end and spent fuel with or without partially burned fuel is to be withdrawn at an opposite end .
  • the Neutron absorbent bodies are then typically held in an arrangement suitable for effecting maximum neutron absorption in an area immediately at or near a part of the reactor core where the fuel passing through the reactor reaches maximum or near maximum neutron flux and a decreasing or zero -To cause neutron absorption in areas adjacent to core areas where the fuel activity is already reduced.
  • the reactor according to the invention is therefore a pebble bed or pebble bed reactor.
  • the level (in relation to the core) at which a change from the maximum absorption effect to a less absorbing or zero absorption effect should take place largely depends on how fuel is supplied to the reactor.
  • the arrangement is intended to provide maximum absorption in an area immediately at or near the top half of the reactor core and reduced or zero absorption in an area where the performance of the non-poisoned core is approximately half to one third of the maximum area Performance is. More specifically, the area with reduced or zero absorption effect begins at a level not less than 1/10 of the total core height above the bottom reflector area of the reactor.
  • the range of maximum performance of the core is usually at a level between 50% and 70% of the total core height and the part of the arrangement with the maximum absorption effect does not extend down to a level 30% of the total core height above the bottom reflector area of the reactor.
  • the reactor is a single-use reactor (OTTO)
  • the range of the maximum output of the core is usually at a level between 66% and 75% of the total core height, with the range of the arrangement with maximum absorption effect downward Level does not extend below 40% of the total core height above the bottom reflector area of the reactor. More specifically, the area of the array with maximum absorption effect extends down to a level not below 50% of the total reactor height above the bottom reflector area of the reactor.
  • areas of the arrangement with maximum absorption effect will be those areas where the neutron absorption bodies as part of the arrangement with normal functioning of the reactor have the largest area of the neutron absorption surface area towards the reactor core, while parts of the arrangement with reduced or zero absorption effect will be those parts where the neutron absorption bodies have a larger area of the weaker neutron absorbing or non-absorbing or reflecting surface area towards the core.
  • the alignment of the neutron absorption bodies in relation to the core is of course also controlled by rotating the bodies between the two extreme orientations for maximum and minimum neutron absorption.
  • the invention is of particular use in reactors where the core's power is used directly to operate helium turbines or turbines with other gaseous media that require high outlet temperatures.
  • the dosage or concentration of fast neutrons hitting the inner wall of the reflector can rise to values above 1.5 x 10 22 cm “2 (EDN). Therefore, in view of the aforementioned modern temperatures, up to 900 ° C or more, a side wall reflector with a continuous, smooth surface also fail before it has reached the designed life expectancy of around 30 years, which is caused by radiation-related graphite volume changes that take place in two phases. In the first phase, neutron radiation leads to an unproblematic volume contraction.
  • the volume increases again, possibly exceeding the original dimensions and resulting in stresses that damage the reflector.
  • the inward-facing surface of the reflector and the corresponding surfaces of the graphite blocks or According to the invention stones are preferably grooved in a manner which is known to compensate for such dimensional changes which the graphite experiences after prolonged intensive neutron irradiation.
  • Figure 1 schematically shows a longitudinal section through a nuclear reactor of the modular HTR pebble type developed according to the invention
  • Figure 2 schematically shows a side view of a nuclear absorption body in an orientation for maximum neutron absorption
  • Figure 3 schematically shows a section at III-III in Figure 2, which shows the neutron absorption body from Figure 2 in a cavity in the active area of the reactor open to the reactor core;
  • Figure 4 schematically shows a partial view of the neutron absorption body shown in Figure 2, coupled to a drive and held at the upper end of an inclined spiral plane, in its orientation for normal functioning of the reactor;
  • FIG. 5 schematically shows a three-dimensional partial view of part of a reflector with the formation of a longitudinal cavity for the mobile reception of a neutron absorption body, the reflector being formed from graphite blocks and the cavity being open towards the reactor core;
  • Figure 6 schematically shows a transverse cross section of part of a reflector for a nuclear reactor, the section running through a neutron absorption body, which is movably accommodated in a cavity formed in the reflector, and through a fuel element in the reactor core.
  • reference numeral 30 generally designates a MODUL-HTR-type pebble (spherical fuel) HTR reactor modified and developed for use in accordance with the present invention.
  • the reactor 30 includes a reactor core 32 filled with poured fuel up to a conical upper level 34.
  • the reference number 36 denotes a reflector made of high-purity graphite in the area of its inner surface and of graphite of lower quality in its outer area.
  • the core 32 and the reflector 36 are from a reactor steel vessel or pressure vessel 38 in connection with a connecting pipe 40 for supplying cooling gas such as helium to the core 32.
  • Reference numeral 42 generally designates a fuel inlet and reference numeral 44 a fuel outlet controlled by an outlet regulator 46.
  • a lower area of the reflector is designated by the reference number 48.
  • the reactor 30 includes a control system for regulating and selectively shutting down the power of the nuclear reactor.
  • the control system includes neutron absorption bodies 52 which are movably housed in cavities 50 formed in the reflector 36.
  • Each neutron absorption body 52 in the embodiment shown has a neutron absorption surface area 54 and a neutron reflecting surface area 56.
  • the neutron absorption surface area may be made of boron carbide, hafnium carbide, or other suitable neutron absorption material.
  • the neutron reflecting surface area can be made of graphite or another suitable neutron reflecting material.
  • the neutron absorption body 52 preferably does not contain any supporting metal parts.
  • the degree of neutron absorption or non-absorption and / or neutron reflection by the neutron absorption body 52 is controlled by controlling the orientation of the absorption body in relation to the reactor core 32 between an extreme orientation for maximum absorption (shown in Figures 2 and 3) at which the neutron absorbing surface area 54 is maximally exposed to the neutron flow from the reactor core 32, and another extreme orientation (shown in Figure 4) for minimal or no neutron absorption and / or for neutron reflection, in which the Neutron reflecting surface area 56 is exposed to the neutron flux.
  • Reference numeral 58 denotes a drive coupled to the neutron absorption body 52 for controlling the alignment of the body 52 by rotating the body between its two extreme orientations.
  • the drive 58 rotates the body 52 within the cavity 50 so that a range of orientations of the neutron absorbing and neutron reflecting surface areas 54, 56 relative to the reactor core 32 can be achieved as is required to control the operation of the reactor 30.
  • the drive 58 is coupled to the body 52 by means of an electromagnetic clutch (not shown).
  • the body 52 is held at the upper end of an inclined spiral plane (reference screw) designated by the reference number 80.
  • the reference number 82 designates a stop or a supplementary bearing surface which interacts with the inclined plane 80.
  • the body 52 moves under gravity, the bearing surface 82 moving downward on the inclined plane 80 and thereby rotating.
  • the reactor is automatically switched off by automatically lowering the neutron absorption bodies 52 into their switch-off positions for maximum neutron flux absorption capacity.
  • the neutron absorption body 52 is shown in its switch-off position after it has moved downward on the support screw 80.
  • the absorption body 52 is held under normal operating conditions at the upper end of the support screw 80 by means of an electromagnetic clutch.
  • Other holding devices or methods for exerting a retaining force on the stop or the support surface 82 in order to hold it at the upper end of the support screw 80 fall within the scope of the invention.
  • Such means are configured for automatic release in the event of a power failure.
  • the actuator 58 is located outside of the pressure vessel 38 of the reactor to facilitate maintenance.
  • the drive is in the pressure vessel.
  • a single longitudinal slot 74 is formed along part of the length of each cavity 50.
  • the slot 74 runs parallel to the reactor core axis and extends rearward from the core area through the cavity 50.
  • Two graphite stones or blocks 76 lying opposite one another are shaped and dimensioned such that a part of the slot 74 and the cavity 50 is formed between them.
  • the slot 74 is shaped and dimensioned in such a way that the neutron absorption body 52 is held captive in the cavity 50, more precisely such that fuel gels 78 (in the case of a pebble bed reactor) cannot get into the cavity.
  • a distance of 20 mm can be achieved between the body 52 and the reactor core 32.
  • the stones or blocks 76 in Figures 5 and 6 form a slot that runs the full vertical length of each stone or block.
  • graphite stones or blocks forming the reflector can each have a discrete slot, so that a vertical stack of stones or blocks forms a series of discrete, successively arranged slots that open to a specific cavity 50 - no.
  • the core-side surfaces 77 of the stones or blocks 76 are grooved in order to compensate for the dimensional changes which graphite undergoes after prolonged intensive neutron irradiation.

Landscapes

  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Chemical & Material Sciences (AREA)
  • Chemical Kinetics & Catalysis (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)
  • Radiation-Therapy Devices (AREA)

Abstract

L'invention concerne un procédé et un système de contrôle pour assurer la régulation et éventuellement couper la puissance d'un réacteur nucléaire. La régulation du système de contrôle se fonde sur l'absorption de neutrons au moyen de corps mobiles d'absorption de neutrons et de corps à faible absorption de neutrons, de corps n'absorbant pas les neutrons ou de corps qui les réfléchissent. Ces corps sont montés mobiles dans des cavités de la zone active du réacteur.
EP00925052A 1999-03-23 2000-03-21 Systeme de commande pour reacteur et procede approprie Withdrawn EP1166277A1 (fr)

Applications Claiming Priority (3)

Application Number Priority Date Filing Date Title
ZA9902246 1999-03-23
ZA9902246A ZA992246B (en) 1999-03-23 1999-03-23 Reactor, control system and method.
PCT/DE2000/000898 WO2000057427A1 (fr) 1999-03-23 2000-03-21 Systeme de commande pour reacteur et procede approprie

Publications (1)

Publication Number Publication Date
EP1166277A1 true EP1166277A1 (fr) 2002-01-02

Family

ID=25587636

Family Applications (1)

Application Number Title Priority Date Filing Date
EP00925052A Withdrawn EP1166277A1 (fr) 1999-03-23 2000-03-21 Systeme de commande pour reacteur et procede approprie

Country Status (4)

Country Link
EP (1) EP1166277A1 (fr)
CN (1) CN1169160C (fr)
WO (1) WO2000057427A1 (fr)
ZA (1) ZA992246B (fr)

Families Citing this family (7)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
RU2555363C9 (ru) * 2009-11-06 2015-10-20 ТерраПауэр, ЭлЭлСи Система и способы регулирования реактивности в реакторе ядерного деления
US9190177B2 (en) 2009-11-06 2015-11-17 Terrapower, Llc Systems and methods for controlling reactivity in a nuclear fission reactor
US9852818B2 (en) 2009-11-06 2017-12-26 Terrapower, Llc Systems and methods for controlling reactivity in a nuclear fission reactor
US9793013B2 (en) 2009-11-06 2017-10-17 Terrapower, Llc Systems and methods for controlling reactivity in a nuclear fission reactor
FR3045199B1 (fr) * 2015-12-15 2018-01-26 Areva Np Grappe absorbante et crayon absorbant pour reacteur nucleaire
CN111081394A (zh) * 2019-12-31 2020-04-28 中国核动力研究设计院 一种小型核反应堆反应性控制装置
CN120126829B (zh) * 2025-04-30 2025-08-01 复旦大学 小型热管堆的反应性控制机构

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Publication number Priority date Publication date Assignee Title
GB803708A (en) * 1955-12-30 1958-10-29 Rolls Royce Improvements in or relating to nuclear reactor control mechanisms
US3151032A (en) * 1960-12-02 1964-09-29 Gen Nuclear Engineering Corp Reactor control device containing poison and fuel
DE3601750A1 (de) * 1986-01-22 1987-07-23 Hochtemperatur Reaktorbau Gmbh Keramische einbauten
DE3631018A1 (de) * 1986-09-12 1988-03-24 Hochtemperatur Reaktorbau Gmbh Verfahren und vorrichtung zum abschalten und moderieren von kernreaktoren mit seitenreflektor

Non-Patent Citations (1)

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Title
See references of WO0057427A1 *

Also Published As

Publication number Publication date
ZA992246B (en) 1999-12-29
CN1352797A (zh) 2002-06-05
WO2000057427A1 (fr) 2000-09-28
CN1169160C (zh) 2004-09-29

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