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41. 发明专利

JP2002357689A BOILING WATER REACTOR WITH BUILT-IN PUMP 失效
公开(公告)号：JP2002357689A
公开(公告)日：2002-12-13
申请号：JP2001167766
申请日：2001-06-04
申请人： TOSHIBA CORP
发明人： YAMAMOTO TETSUZO , NARABAYASHI SUNAO , SAITO NOBORU , HAGIWARA TAKESHI , HIRUKAWA ATSUJI , YAMADA KATSUMI , KONDO TAKAHISA
IPC分类号： G21C15/243 , F04D29/54 , G21C15/02 , G21C17/032
摘要： PROBLEM TO BE SOLVED: To reduce a loss of power supply to a recirculation pump by minimizing a pressure loss accompanying a flow near the recirculation pump. SOLUTION: This building water reactor comprises a pressure vessel 1, a pump deck 3 for forming the bottom part of an annular downcomer part sandwiched between the pressure vessel and a shroud, and two or more recirculation pump 2 juxtaposed through the pump deck. A tapered nozzle 22 connected to the sucking side of the recirculation pump while gently changing the passage area is arranged above the recirculation pump, and the inlet part of the tapered nozzle is flattened long along the circumferential direction of the downcomer part. A shroud support leg 6 for supporting the lower part of the shroud to the bottom part of the pressure vessel under the pump deck comprises an opening part 8 corresponding to each recirculation pump and a guide plate 33 for smoothly guiding the discharge flow from each recirculation pump to the opening part.

42. 发明专利

JPH11133176A FUEL ASSEMBLY 失效
公开(公告)号：JPH11133176A
公开(公告)日：1999-05-21
申请号：JP16758598
申请日：1998-06-15
申请人： TOSHIBA CORP
发明人： AKIBA YOSHIYUKI , TSUKUMO YOSHIAKI , NIITOME TOKUJI , MOROOKA SHINICHI , NARABAYASHI SUNAO , SHIRAKAWA TAKEETSU , YAMAMOTO YASUSHI , MIURA SHIGERU , KUBO SHINJI , HOSHIIDE AKIHIKO , OMIZU SATOSHI
IPC分类号： G21C3/33 , G21C3/30 , G21C3/32
摘要： PROBLEM TO BE SOLVED: To provide a fuel assembly enabling foreign-matter catching efficiency to be set sufficiently high, having little pressure loss, and capable of maintaining soundness effectively by surely preventing foreign matters accompanying coolant from flowing into the fuel assembly. SOLUTION: This fuel assembly has a plurality of fuel rods 2, an upper tie plate 4 and lower tie plate 5 for supporting upper and lower ends of the fuel rods, a plurality of spacers 8 disposed at intervals between the two tie plates for holding distances between the fuel rods, and a channel box 1 covering the outer circumference of the whole body, and causes coolant flowing in from the lower end side of the lower tie plate to flow as an ascending current to the fuel rod side. A spiral blade part 22 disposed in a center position of a lower part of the lower tie plate and structured to have a center hub 23 and a plurality of blades 24 for causing the ascending coolant to be a swirling current, and a vertical cylinder body 21 building up as high as a fixed height position on the back wash side of the spiral blade part with its upper and lower end opened are provided. A foreign-matter recovering part 25 is formed on an outside lower part of the cylinder body on the inner surface side of the lower tie plate for dropping to recover foreign matters flowing into the lower tie plate together with the coolant.

43. 发明专利

JPH1114787A MAIN STEAM RELIEF VALVE OF NUCLEAR POWER PLANT 失效
公开(公告)号：JPH1114787A
公开(公告)日：1999-01-22
申请号：JP16460797
申请日：1997-06-20
申请人： TOSHIBA CORP
发明人： IWANAGA MASAKAZU , TOKUNAGA TAKASHI , YAMADA KATSUMI , NARABAYASHI SUNAO , TANAKA NOBUHIKO
IPC分类号： G21D1/00
摘要： PROBLEM TO BE SOLVED: To improve the reliability of valve operation and earthquake resistance, make a valve into a smaller and compact size, and improve the maintenance property by integrating a forced operation device into a valve body. SOLUTION: An operation actuator 27 is formed of a spring operation actuator 32 and a fluid-pressure operation actuator 30, and both the actuators 30, 32 are integrally constituted with a valve bar 28 as a common shaft. In the fluid-pressure operation actuator 30, a piston 40 is housed within a cylinder case 31 in such a manner as to, be capable of rising and falling, and a cylinder chamber 41 is formed in the lower part to supply a working fluid such as air or nitrogen through a feed port 42. When the pressure within a reactor pressure vessel is raised to a prescribed pressure by any cause, the fluid-pressure operation actuator 30 is operated by an external signal to raise the piston 40. The valve bar 28 is forcedly raised against the spring force of a spring 37 by the rise of the piston 40, and a main steam relief valve 20 is forcedly opened to release a part of the main steam.

44. 发明专利

JPH09243779A NUCLEAR REACTOR 失效
公开(公告)号：JPH09243779A
公开(公告)日：1997-09-19
申请号：JP5213196
申请日：1996-03-08
申请人： JAPAN ATOMIC POWER , TOSHIBA CORP
发明人： YOSHIOKA YUZURU , KADOTANI MITSUTO , TABATA HIROAKI , SUGANO MINORU , YOSHIHISA YASUMASA , NARABAYASHI SUNAO , ARAI KENJI , YANO TAKASHI , SHIOIRI AKIO , OIKAWA HIROHIDE , MIZUMACHI WATARU , YASUOKA MAKOTO
IPC分类号： G21C15/18
摘要： PROBLEM TO BE SOLVED: To properly cope with a minor rupture accident and improve the safety and economic property of a nuclear reactor by injecting water into a reactor vessel by a steam injector. SOLUTION: When a minor rupture accident occurs, an automatic pressure reducing system 5 or an isolation condenser is operated to reduce the internal pressure of a reactor pressure vessel 2. When the internal pressure of the vessel 2 is lowered to a prescribed value, a low pressure core water injecting system 16 is operated. After several minutes from operation start, combining water from a steam injector 17 is injected into the vessel 2. The internal pressure of the vessel 2 is lowered by water injection of the water injecting system 16, and when the downstream side pressure of a check valve 14 becomes lower than the head pressure of a pool 11, the valve 14 is opened to inject water in the pool 1 into the vessel 2 through a piping 12. Just after the occurrence of the minor rupture accident, the level in the vessel is recovered and kept by water injection of the water injecting systems 16, 10 to ensure the cooling of a core 3. The steam in the vessel 2 is released into the dry well DW of a reactor container 1 to ensure a long-term cooling.

45. 发明专利

JPH07119700A JET PUMP 失效
公开(公告)号：JPH07119700A
公开(公告)日：1995-05-09
申请号：JP26365393
申请日：1993-10-21
申请人： TOSHIBA CORP
发明人： NARABAYASHI SUNAO , NEI HIROMICHI , IWANAGA MASAKAZU , MIZUMACHI WATARU , TANABE AKIRA
IPC分类号： G21C15/25 , F04F5/10 , F04F5/46
摘要： PURPOSE:To reduce a pressure loss and cavitation by providing plural outer peripheral side nozzle parts projected to the suction side on the outside concentric circle of a center side nozzle part, and making the respective outer peripheral side nozzle parts shorter than the center side nozzle part. CONSTITUTION:A multi-stage accelerating rotary driven water nozzle 32 is so constructed that a center nozzle 36 is provided in the shaft center part, and outer peripheral rotary nozzles 37a-37d which are plural outer peripheral side nozzle parts are disposed in the circumferential direction by equal pitches on the concentric circle on the outside of the center nozzle. The center nozzle 36 and the outer peripheral rotary nozzles 37a-37d are connected integrally to each other by branch pipes 38a-38d projected radially on the side of the center nozzle 36. Further, the length of projection of each outer peripheral rotary nozzle 37a-37d is made a little smaller than that of the center nozzle 36, and the central axis ''a of the center nozzle 36 is coaxially aligned with the central axis Ob of a diffuser. Thus, a fluid can be accelerated by different sections so as to decrease a pressure loss.

46. 发明专利

JPH05288881A 失效
公开(公告)号：JPH05288881A
公开(公告)日：1993-11-05
申请号：JP8564392
申请日：1992-04-07
申请人： TOSHIBA CORP
发明人： SAITO NOBORU , NARABAYASHI SUNAO , YAMADA KATSUMI , TANAKA NOBUHIKO , MIYAGAWA TAKUYA , TSUZUKI RITSUKO , AIDA YASUHIKO
IPC分类号： G21C7/14
摘要： PURPOSE:To ensure an area of movement of a control rod in the upper part of a core and to enable insertion of the control rod from above a fuel assembly. CONSTITUTION:A control rod guide tube 25 holding a control rod 24 inside is provided in a space between cylindrical bodies constituting a steam separator 9 and a stand pipe 8. This control rod guide tube 25 pierces through a core shroud head 7 and is disposed in the form of an integrated body to the upper end of a fuel assembly 6.

47. 发明专利

JPH0587971A EMERGENCY CORE COOLING SYSTEM OF NUCLEAR REACTOR 失效
公开(公告)号：JPH0587971A
公开(公告)日：1993-04-09
申请号：JP24779291
申请日：1991-09-26
申请人： TOSHIBA CORP
发明人： KATAOKA KAZUYOSHI , NARABAYASHI SUNAO , ARAI KENJI
IPC分类号： G21C15/18
摘要： PURPOSE:To enable highly reliable water injection into a reactor core during reactor accident for a high pressure range to a low pressure range thereof, without any additional dynamic equipments which require very high reliability. CONSTITUTION:At a position higher than a reactor core 14 in a nuclear reactor pressure vessel 13, a gravity falling type core cooling system pool 17 is installed in a nuclear reactor containment vessel 1. Beneath the cooling system pool 17, a pressure suppression pool 15 is also installed and a steam injector 2 is installed in a dry well of the nuclear reactor containment vessel 1, as well. This steam injector 2 is connected to a steam feed line 4 which is connected to the nuclear rotor pressure vessel 13, a steam discharge line 5, a feed water line 3 which is connected to the gravity falling type core cooling system pool 17, and a drain line 36 which is connected to the pressure suppression pool 15, and also both a reducing valve 20 of the steam feed line 4 and a control valve 6 of the feed water line 4 are connected to a controller 38 through signal leads 39 and 40.

48. 发明专利

JPH03282072A SHAFT SEALING DEVICE FOR PUMP 失效
公开(公告)号：JPH03282072A
公开(公告)日：1991-12-12
申请号：JP7883990
申请日：1990-03-29
申请人： TOSHIBA CORP
发明人： NARABAYASHI SUNAO , MIYANO HIROSHI , KOBASHI KAZUYUKI , YAMAMOTO TETSUZO , ISHIYAMA TAKENORI , TANAKA NOBUHIKO
IPC分类号： F04D29/10 , F16J15/34 , F16J15/447
摘要： PURPOSE:To sharply improve reliability on structural strength by providing a shaft seal water cooling device to cool shaft seal water in the vicinity of the upper part of a casing cover and a shaft seal heating device to heat shaft seal water in the vicinity of the lower part of the casing cover. CONSTITUTION:A shaft seal cooling device 21 to cool shaft seal water in a seal chamber 3 is mounted to the side of a shaft sleeve 20a and a shaft seal water heating device 22 to heat shaft seal water is located to the under surface of a casing cover 14. A pump action by a centrifugal force is created by means of a plurality of longitudinal grooves 39 formed in a part of a pump shaft 2. Hot pump water is discharged through pores formed in a rotary cylinder 20c of the shaft seal water heating device 22 in a manner to cover the longitudinal grooves 39 therewith, and by mixture of pump water (hot water) with shaft seal water (cold water), the temperature increase effect of the shaft seal water is produced. Hot water discharged from an underwater bearing 15 is caused to flow through a heating cylinder 37 located to the lower part of the casing cover 14.

49. 发明专利

JPH0375593A NUCLEAR POWER PLANT 失效
公开(公告)号：JPH0375593A
公开(公告)日：1991-03-29
申请号：JP21058889
申请日：1989-08-17
申请人： TOSHIBA CORP
发明人： NARABAYASHI SUNAO , NEI HIROMICHI , TANABE AKIRA , TONEGAWA REI
IPC分类号： G21C1/08 , G21C15/18 , G21C15/25 , G21C15/26
摘要： PURPOSE:To promote natural circulation of coolant to a reactor core, to simplify the system and to improve the safety by spouting water delivered from a steam injector connected to a nuclear reactor pressure vessel, to a down comer in the vessel. CONSTITUTION:Steam heated at the reactor core 1 in a nuclear reactor pressure vessel 2, is transferred to a turbine 7 where it is used as an energy source and then is transferred to a main condenser 9. To the outlet side of the condenser 9, a steam injector 10 for water supply, is connected and in the upstream of a water supply pipe 13, a recirculation injector 14 is provided for a downcomer in the vessel. The injection 10 and 14 are actuated by steam supply from a main steam pipe 8, for instance, and supplies coolant to the vessel 2 of the condenser 9 and also spouts high pressure coolant into the downcomer in the vessel 2, thus cooling down the reactor core 1 through recirculation. In this way, by feeding water to each system utilizing the steam injections 10, 14, 19, 24 and 26 which do not require an external power supply and have no moving parts, the system can be simplified and the size of the building can be reduced and finally the safety can be much improved.

50. 发明专利

JPH0295299A NUCLEAR REACTOR CONTAINMENT 失效
公开(公告)号：JPH0295299A
公开(公告)日：1990-04-06
申请号：JP24695688
申请日：1988-09-30
申请人： TOSHIBA CORP
发明人： NARABAYASHI SUNAO , TAKAHASHI HIDEAKI , SAITO NOBORU
IPC分类号： G21C9/00
摘要： PURPOSE:To speedily and stably cool the containment for a long period after a cooling material losing accident by consisting an outer peripheral containment pool of small-sized section outer peripheral containment pools. CONSTITUTION:The outer peripheral containment pool 48 consists of the small- sized section outer peripheral containment pools 49 which are arranged in the height direction and circumferential direction of the external wall of the containment 46 and the water in an upper water supplement pool 50 is supplied to the section outer peripheral pools 49 through water supplement pipe 51, water supplement branching pipes 52, and a float valve 53 to secure a constant pool water level 54. Further, the section outer peripheral pools 49 are open to the air through an atmospheric vent pipe 55 and the water temperature of the section outer peripheral pools 49 is limited to 100-110 deg.C. Then, heat generated in the containment 46 is conducted to the wall of the containment 46 and further conducted to the water in the outer peripheral pool 48. In the outer peripheral pool 48, a natural circulation flow is generated and boiling is caused in the internal wall of the pool to cool the containment 46 with the boiling latent heat.

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