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1. 发明专利

JPS6250686A TAKAMAK TYPE NUCLEAR FUSION REACTOR 失效
公开(公告)号：JPS6250686A
公开(公告)日：1987-03-05
申请号：JP19108185
申请日：1985-08-30
申请人： KAWASAKI HEAVY IND LTD , JAPAN ATOMIC ENERGY RES INST , HITACHI LTD , TOSHIBA CORP , MITSUBISHI ATOMIC POWER IND , MITSUBISHI HEAVY IND LTD
发明人： ADACHI JUNICHI , KOBAYASHI TAKESHI , MIZOGUCHI TADANORI , MORI SEIJI , SATO KATSUTOSHI , UCHIDA TAKAO , HONDA TSUTOMU , YAMADA MASAO , IMAMURA YUTAKA
IPC分类号： G21B1/11 , G21B1/00 , G21B1/25 , H05H1/12

3. 发明专利

JPH01207694A NUCLEAR FUSION DEVICE 失效
公开(公告)号：JPH01207694A
公开(公告)日：1989-08-21
申请号：JP3302288
申请日：1988-02-16
申请人： JAPAN ATOMIC ENERGY RES INST , TOSHIBA CORP
发明人： NISHIO SATOSHI , IIDA HIROMASA , HONDA TSUTOMU
IPC分类号： G21B1/05 , G21B1/00 , G21B1/13
摘要： PURPOSE:To stabilize tritium breeding by providing an outside piping to the outside circumferential side of a cooling piping apart a spacing therefrom and winding a wire spirally on the outside circumference of the cooling piping in order to maintain the spacing between the outside piping and the cooling piping. CONSTITUTION:The outside piping 108 is disposed on the outside circumferential side of the cooling piping 107. This piping 108 is cut at prescribed intervals and are constituted of plural short pipes 108A in order to absorb thermal expansion. A projection 109 is provided on one end face of the pipe 108A and the adjacent short pipe 108A is so constituted that the tight contact of the end face thereof is prevented by the projection 109. The wire 110 is spirally wound on the outside circumference of the piping 107 and the spacing between the pipings 107 and 108 is surely held. The piping 108 is provided on the outside circumferential side of the piping 107 apart the prescribed spacing in such a manner and, therefore, the temp. difference between the piping 107 and a tritium breeder 106 is sufficiently maintained. The tritium breeding is thereby stabilized.

4. 发明专利

JPH0519076A NUCLEAR FUSION REACTOR 失效
公开(公告)号：JPH0519076A
公开(公告)日：1993-01-26
申请号：JP17281291
申请日：1991-07-12
申请人： TOSHIBA CORP , JAPAN ATOMIC ENERGY RES INST
发明人： KONDOU MITSUNORI , HONDA TSUTOMU , SHIBANUMA KIYOSHI
IPC分类号： G21B1/05 , G21B1/00
摘要： PURPOSE:To enable improvement of a rate of operation of a reactor by a construction wherein an insertion port for insertion of an observing device of the inside of the reactor is so provided as to communicate with the inside and outside of a vacuum vessel holding plasma and a movable shield plug for opening and closing the insertion port is driven by a driving device. CONSTITUTION:A movable shield plug 1 is pulled out in the vertical direction to the position of opening by operating a hydraulic cylinder driving device 3. Then an wedge-shaped opening 106b of a shielding body 106 opens and a blocking flange 6 is removed from the outer end of an insertion port pipe 111a. An observing device 113 of the inside of a reactor is inserted from an insertion port 111 and thereby checkup and observation of the inside of the furnace are conducted. Since the port 111 is opened and closed by moving the plug 1 forward and backward between the position of opening and that of closure by the device 3, in this way, it can be opened and closed quickly and thus a rate of operation of the reactor can be made high.

5. 发明专利

JPH01151200A NEUTRAL PARTICLE INCIDENCE HEATING DEVICE 失效
公开(公告)号：JPH01151200A
公开(公告)日：1989-06-13
申请号：JP30773187
申请日：1987-12-07
申请人： JAPAN ATOMIC ENERGY RES INST , TOSHIBA CORP
发明人： SHIBANUMA KIYOSHI , YAMAMOTO ARATA , NAKAJIMA KUNIHIKO , HONDA TSUTOMU
IPC分类号： H05H1/22 , G21B1/00 , G21B1/11
摘要： PURPOSE:To reduce the load to a tritium fuel processing system and make its capacity small by providing an exhaust circulating system returning the exhaust gas from an ion source exhaust system to an ion source. CONSTITUTION:In a neutral particle incidence heating device 2, the exhaust gas from an ion source exhaust system 14 is guided into a gas purifying device 103 via a circulating pipeline 102 and refined there then returned to an ion source 109 via the circulating pipeline 102. The capacity of a tritium fuel processing system 5 is thus made small. The tritium concentration of the exhaust gas exhausted from the exhaust system 14 is low, i.e., it is the large flow of the heavy hydrogen gas, when it is transferred to the processing system 5, the capacity of the processing system 5 is made large, but it is returned to the ion source 9 via an exhaust circulating system 101, thereby the capacity of the processing system 5 can be effectively made small.

6. 发明专利

JPS60173494A NUCLEAR FUSION DEVICE 失效
公开(公告)号：JPS60173494A
公开(公告)日：1985-09-06
申请号：JP2983784
申请日：1984-02-20
申请人： JAPAN ATOMIC ENERGY RES INST , TOSHIBA KK
发明人： NISHIO SATOSHI , HONDA TSUTOMU
IPC分类号： G21B1/11 , G21B1/00 , G21B1/13

7. 发明专利

JPS5999287A NUCLEAR FUSION DEVICE 失效
公开(公告)号：JPS5999287A
公开(公告)日：1984-06-07
申请号：JP20906582
申请日：1982-11-29
申请人： JAPAN ATOMIC ENERGY RES INST , TOSHIBA KK
发明人： TONE TATSUZOU , NISHIO SATOSHI , HONDA TSUTOMU , EBISAWA KATSUYUKI
IPC分类号： G21B1/13 , G21B1/00

8. 发明专利

JPS6473289A NUCLEAR FUSION REACTOR 失效
公开(公告)号：JPS6473289A
公开(公告)日：1989-03-17
申请号：JP22946087
申请日：1987-09-16
申请人： TOSHIBA CORP
发明人： KONDOU MITSUNORI , EBISAWA KATSUYUKI , HONDA TSUTOMU , KOBAYASHI SHIGETADA , HATAYAMA AKIMASA , TACHIKAWA NOBUO , SAITO YASUSHI
IPC分类号： G21B1/05 , G21B1/00 , G21B1/11
摘要： PURPOSE:To obtain a highly safe nuclear fusion reactor with a better controllability of plasma with the simplification of a core construction and a cooling system, by employing a liquid nitrogen cooled superconductive coil in a coil system to cool a blanket, a shielding body and a coil by liquid nitrogen. CONSTITUTION:A shielding body 30 incorporates a vacuum container 1 holding a plasma 2 inside, a coil system such as a toroidal coil 31 comprising a liquid nitrogen cooled superconductive coil, a poloidal coil 46, a current transformer coil 47 and a diverter coil 51 and a blanket 33. The coil system and a cooling piping 50 for cooling the blanket 33, the shielding body 30 and the diverter 52 are arranged inside. The shielding body 30 is supported with a support column 32. This simplifies a core construction and a cooling system thereby achieving a higher controllability of plasma. There is also no such a member as splitting the support column thereby achieving a higher reliability for an earthquake or the like.

9. 发明专利

JPS63275985A COOLING APPARATUS OF FUSION REACTOR SYSTEM 失效
公开(公告)号：JPS63275985A
公开(公告)日：1988-11-14
申请号：JP11082487
申请日：1987-05-08
申请人： TOSHIBA CORP
发明人： HONDA TSUTOMU
IPC分类号： G21B1/05 , G21B1/00
摘要： PURPOSE:To maintain a cooling function even if abnormality occurs in one cooling system in a rare possibility, by providing two cooling apparatuses in a fusion reactor system, and using divided modules for a torus structure part for every other piece. CONSTITUTION:Heat of an operating torus structure part 5 in a fusion reactor and residual heat after stopping are cooled with a first cooling system for modules 5A, 5C, 5E and 5G and cooled with another second cooling system for modules 5B, 5D, 5F and 5H. If leakage of coolant and the like occur due to the trouble of, e.g., a pump 17A, and breakdown of a main pipe 14A or 15A and the cooling ability is lost, the modules 5A, 5C, 5E and 5G are no longer cooled, but the modules 5B, 5D, 5F and 5H are still cooled since the second cooling system is operating. The heat in the modules 5A, 5C, 5E and 5G, which are located between above described modules, is removed by the conduction and radiation to the modules 5B, 5D, 5F, and 5H.

10. 发明专利

JPS6439588A NUCLEAR FUSION EQUIPMENT 失效
公开(公告)号：JPS6439588A
公开(公告)日：1989-02-09
申请号：JP19520187
申请日：1987-08-06
申请人： TOSHIBA CORP
发明人： HONDA TSUTOMU , EBISAWA KATSUYUKI , KOBAYASHI SHIGETADA , HATAYAMA AKIMASA , KONDOU MITSUNORI , TACHIKAWA NOBUO , SAITO YASUSHI
IPC分类号： G21B1/11 , G21B1/00 , H05H1/12
摘要： PURPOSE:To improve controllability by using a liquid nitrogen cooled superconductive coil to constitute a coil for plasma position control. CONSTITUTION:The coil 101 for plasma position control is constituted of the liquid nitrogen cooled superconductive coil and is integrated with a vacuum vessel 1 and is embedded via a heat insulating material consisting of ceramics, etc., into the grooves on a lead pipe near the outside circumference of the front and rear faces of the vessel 1. Controllability is improved by installing the coil 101 in proximity to plasma 12 in such a manner.

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