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1. 发明专利

JPH11248872A REACTOR CORE AND METHOD FOR OPERATING IT 失效
公开(公告)号：JPH11248872A
公开(公告)日：1999-09-17
申请号：JP5470998
申请日：1998-03-06
申请人： HITACHI LTD , HITACHI ENG CO LTD
发明人： NARITA TAKEMI , MOCHIDA TAKAAKI , NAKAMURA MITSUYA , NAKAYAMA KATSUYUKI , ISHIHARA NAOYUKI
IPC分类号： G21C5/00 , G21C7/08
摘要： PROBLEM TO BE SOLVED: To provide a reactor core, a method for loading fuels and that for operating a reactor that can secure thermal allowance and are excellent in fuel economy without inserting control rods in early and last periods of an operation cycle to secure the thermal allowance. SOLUTION: Basic units 21 shaped like a square are configured by locating two new fuels (for the first cycle) 1 and 1a and two fuels for the third cycle 3 so that new fuels cannot adjoin each other and the fuels for the third cycle 3 cannot do so. One fifth or more of a core is constituted of the basic unit 21. Then, the core is composed so that four fuels 2 for the second cycle 2 can adjoin the new fuels 1 and la in the center zone that accounts for about 70% in the radial direction of the core.

2. 发明专利

JP2000162365A DEVICE FOR CALCULATING REACTOR CORE PERFORMANCE OF REACTOR 失效
公开(公告)号：JP2000162365A
公开(公告)日：2000-06-16
申请号：JP33527298
申请日：1998-11-26
申请人： HITACHI LTD , HITACHI ENG CO LTD
发明人： NARITA TAKEMI , NAKAMURA MITSUYA , KONOMA AKIRA , SHIRAGAMI HISASHI
IPC分类号： G21C17/00
摘要： PROBLEM TO BE SOLVED: To automatically and internally calculate a target critical characteristic value for setting by using a value being determined according to the degree of reactor core average combustion, relative reactor core heat output, a reactor core average deceleration material void rate, and relative heat output in the reactor core of an axial node position adjacent to the control rod of a fuel assembly, and reactor core average xenon concentration as an index. SOLUTION: A control rod insertion pattern, reactor core flow rate, or the like is taken into an input processing part 2 from reactor 7, and also information on in-pipe neutron bundle distribution is taken into the input processing part 2 from an in-pipe neutron measuring instrument 9. Reactor core performance is calculated by a three-dimensional calculation part 3, and data is stored into a reactor core performance achievement data storage part 4. In reactor performance estimation calculation, parameters such as reactor core heat output, a reactor core flow rate, a control rod pattern, and an estimation date required for estimation calculation are inputted into the input processing part 2 by a user, and three-dimensional reactor core calculation is made at a three-dimensional reactor core calculation part 3. Based on the result and the reactor core performance achievement data of an estimation start point being stored into the actual result data storage part 4, the data from database 6 for calculating a target critical characteristic value is used for calculating the characteristic value at a critical characteristic value calculation part 5.

3. 发明专利

JPH10253789A FUEL ASSEMBLY AND CORE 失效
公开(公告)号：JPH10253789A
公开(公告)日：1998-09-25
申请号：JP5511497
申请日：1997-03-10
申请人： HITACHI LTD
发明人： NARITA TAKEMI , HAIKAWA KATSUMASA , YAMANAKA AKIHIRO , KANDA AKIKO , MOCHIDA TAKAAKI , YAMASHITA JUNICHI
IPC分类号： G21C5/00 , G21C3/326 , G21C3/328 , G21C5/12 , G21C7/00
摘要： PROBLEM TO BE SOLVED: To suppress maximum linear power density in control rod side region below a limit value after the withdrawal of control rods even in the case aiming at high burnup. SOLUTION: A diagonal (m) separating the inside of a fuel assembly 1L into the control rod 11 side region and the opposite of control rod 11 side region is drawn to divide into the third region 8 including the 6 fuel rods 4 and 2 water rod on this diagonal (m), the first region 6 in control rod 11 side of the third region 8 and the second region 7 of the opposite side of the control rod 11. In the whole cross section plane positioning lower axial part (1/24 to 10/24), the average enrichment of whole 34 fuel rods 4 existing in the second region 7 is larger by 14% than the average enrichment of whole 34 fuel rods 4 existing in the first region 6. Also in the whole cross section plane positioning upper axial part (11/24 to 22/24), the average enrichment of whole fuel rods 4 existing in the second region 7 is made larger by 7% than the average enrichment of whole fuel rods 4 existing in the first region 6.

4. 发明专利

JP2001004775A GANG CONTROL ROD CONTROLLER 失效
公开(公告)号：JP2001004775A
公开(公告)日：2001-01-12
申请号：JP17629499
申请日：1999-06-23
申请人： HITACHI LTD
发明人： NARITA TAKEMI , NAKAMURA MITSUYA , YAMANAKA AKIHIRO , HAIKAWA KATSUMASA
IPC分类号： G21C7/08 , G21C17/10
摘要： PROBLEM TO BE SOLVED: To provide a gang control rod controller which minimizes increase of startup time in a gang control rod controller in which the minimum drive step width of a control rod is increased. SOLUTION: In a gang control rod controller consisting of a gang control rod operation device 1 for determining the selection, insertion and withdrawal of a plurality of control rods to be simultaneously operated by control information and a control rod drive controller 2 for driving the control rods, the gang control rod operation device 1 stores at least two kinds of group separation information including a group separation gradually decreasing in number as grouping of gang control rods simultaneously operated in the range where almost half of total control rods are withdrawn in a checker board pattern without including the central control rod.

5. 发明专利

JPH1082880A NUCLEAR REACTOR OPERATING METHOD 失效
公开(公告)号：JPH1082880A
公开(公告)日：1998-03-31
申请号：JP23615496
申请日：1996-09-06
申请人： HITACHI LTD
发明人： NARITA TAKEMI , HAIKAWA KATSUMASA , YAMANAKA AKIHIRO , KANDA AKIKO , MOCHIDA TAKAAKI , YAMASHITA JUNICHI , KOYAMA JUNICHI
IPC分类号： G21C5/00 , G21C7/00
摘要： PROBLEM TO BE SOLVED: To provide a nuclear reactor operating method that can attain high burn-up of fuel assemblies low in average enrichment and ensure thermal allowance. SOLUTION: In the first cycle, the nuclear reactor is operated inserting a control rod in a first control cell 4 formed of a low enrichment fuel 2 but without inserting a control rod in a second control cell 3 formed of a high enrichment fuel 1. After completing the operation of the first cycle, fuel assemblies are moved in the reactor core without charging new fuel. The nuclear reactor is then operated in the greater part of the second cycle period inserting a control rod in the second control cell 3 but without inserting a control rod in the first control cell 4.

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