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1. 发明专利

JP2006329709A Nuclear reactor output control method and apparatus thereof 有权
标题翻译：核反应堆输出控制方法及装置
公开(公告)号：JP2006329709A
公开(公告)日：2006-12-07
申请号：JP2005151151
申请日：2005-05-24
申请人： Hitachi Ltd , 株式会社日立製作所
发明人： IWATA YUTAKA , YUNOKI MASAICHI
IPC分类号： G21C7/08 , G21C17/10 , G21D3/00
CPC分类号： Y02E30/39
摘要： PROBLEM TO BE SOLVED: To suitably execute the heating-up operation of a nuclear reactor with a specified reactor water temperature changing rate maintained even if a moderator has a positive temperature coefficient. SOLUTION: The reactor period is calculated on the basis of a detected neutron flux by a neutron flux monitor 26, and the reactor water temperature changing rate is calculated on the basis of a detected reactor water temperature by a temperature changing rate calculator 22. Further, the temperature rise acceleration as an acceleration of the reactor water temperature changing rate is calculated. (1) When the reciprocal of the reactor period is not smaller than a set value and simultaneously the reactor water temperature changing rate is not smaller than an insertion decision guideline set value (a), or (2) when the reciprocal of the reactor period is not smaller than the set value and further the reactor water temperature changing rate exceeds another insertion decision set value b (b d), which is different from the value d, and simultaneously the temperature rise acceleration is smaller than the set value, the control rod is withdrawn. COPYRIGHT: (C)2007,JPO&INPIT
摘要翻译：要解决的问题：即使调节剂具有正温度系数，也能够适当地执行具有规定的反应器水温变化率的核反应堆的升温操作。解决方案：基于由中子通量监测器26检测的中子通量来计算反应器周期，并且基于通过温度变化率计算器22检测到的反应器水温计算反应器水温变化率此外，计算作为反应器水温变化率的加速度的升温加速度。（1）当反应堆周期的倒数不小于设定值，同时反应堆水温变化率不小于插入决策指标设定值（a）时，或（2）反应堆周期的倒数时不小于设定值，并且反应器水温变化率进一步超过与设定值（a）不同的另一插入判定设定值b（b d），同时温升加速度小于设定值，控制棒为取消。版权所有（C）2007，JPO＆INPIT

2. 发明专利

JP2005227025A Reactor power control method and system 有权
标题翻译：反应堆功率控制方法与系统
公开(公告)号：JP2005227025A
公开(公告)日：2005-08-25
申请号：JP2004033693
申请日：2004-02-10
申请人： Hitachi Ltd , 株式会社日立製作所
发明人： OCHI HITOSHI , YUNOKI MASAICHI
IPC分类号： G21C7/08 , G21C17/00 , G21C17/02 , G21C17/10
CPC分类号： Y02E30/39
摘要： PROBLEM TO BE SOLVED: To maintain reactor pressure and reactor water temperature at constant states during intervals of a raising process of temperature and pressure which is performed in a plurality of steps for reactor power control.
SOLUTION: In the reactor power control step, a terminal target reactor pressure is reached by setting individual intermediate target reactor pressures, repeating step by step temperature/pressure rising control and by operating control rods so as to maintain specific reactor water temperature variation rate and reaching the intermediate target reactor pressures. The control rods are to be operated when the difference between an insertion length and a withdrawal length of the control rods until reaching the target reactor pressure in the previous temperature/pressure rising process is within a set value range, after reaching the target reactor pressure in the previous temperature/pressure rising process between the previous process and the next process, and when the difference between a neutron flux detection value at the final control rod operation performed until reaching of the target reactor pressure in the previous temperature/pressure rising process, and a neutron flux detection value at a time elapsed for a certain time from the final control rod operation, is within a set value range.
COPYRIGHT: (C)2005,JPO&NCIPI
摘要翻译：要解决的问题：在反应堆功率控制的多个步骤中进行的温度和压力升高过程的间隔期间，将反应堆压力和反应堆水温度保持在恒定状态。解决方案：在反应堆功率控制步骤中，通过设定各个中间目标反应堆压力，重复一步一步的温度/升压控制和操作控制棒来达到终端目标反应器的压力，以保持特定的反应器水温变化速率并达到中间目标反应堆的压力。当控制棒的插入长度和取出长度之间的差异直到在先前的温度/压力上升过程中达到目标反应器压力之间的差值在达到目标反应器压力之后时，控制杆将被操作以前的过程和下一个过程之间的先前的温度/压力上升过程，以及当在前一个温度/压力上升过程中直到达到目标反应器压力的最终控制棒操作的中子通量检测值之间的差异以及从最终控制杆操作经过一段时间的中子通量检测值处于设定值范围内。版权所有（C）2005，JPO＆NCIPI

3. 发明专利

JP2007064946A Method and device for determining positive/negative of moderator temperature coefficient 有权
标题翻译：用于确定调节器温度系数的积极/否定的方法和装置
公开(公告)号：JP2007064946A
公开(公告)日：2007-03-15
申请号：JP2005255079
申请日：2005-09-02
申请人： Hitachi Ltd , 株式会社日立製作所
发明人： IWATA YUTAKA , YUNOKI MASAICHI
IPC分类号： G21C17/108
摘要： PROBLEM TO BE SOLVED: To provide a method and device for determining positive/negative of the moderator temperature coefficient before output control by control rod operation is required. SOLUTION: A neutron flux monitor 26 calculates a reactor period based on a value of a neutron flux detected from a reactor 1 with a neutron flux detector 12, and a reactor water temperature difference calculation apparatus 29 calculates reactor water temperature difference occurring while the control rod drive stopping state continues. When the inverse number of the reactor period is a preset value or more, the reactor water temperature difference is a preset value or higher, and the control rod drive stopping state continues for a certain time or longer, a positive/negative determining apparatus 35 determines that the moderator temperature coefficient is positive. When the inverse number of the reactor period is the preset value or less, the reactor water temperature difference is the preset value or higher, the control rod drive stopping state continues for the preset certain time or longer, and the last driving before stop of the control rod is performed in the pulled direction, the moderator temperature coefficient is determined to be negative. COPYRIGHT: (C)2007,JPO&INPIT
摘要翻译：要解决的问题：提供一种用于通过控制杆操作输出控制之前确定调节器温度系数的正/负的方法和装置。解决方案：中子通量监测器26基于从具有中子通量检测器12的反应器1检测的中子通量的值计算反应器周期，反应器水温差计算装置29计算反应器水温差发生的差异控制杆驱动停止状态继续。当反应器周期的倒数为预设值以上时，反应器水温差为预设值以上，控制棒驱动停止状态持续一定时间以上，正/负判定装置35判定为主持人温度系数为正。当反应堆周期的倒数为预设值或更小时，反应堆水温差为预设值或更高，控制棒驱动停止状态持续预设一定时间或更长时间，停止前的最后一次驾驶控制杆在拉动方向上进行，调节器温度系数确定为负值。版权所有（C）2007，JPO＆INPIT

4. 发明专利

JP2005241384A Method and device for controlling nuclear reactor output 有权
标题翻译：用于控制核反应堆输出的方法和装置
公开(公告)号：JP2005241384A
公开(公告)日：2005-09-08
申请号：JP2004050373
申请日：2004-02-25
申请人： Hitachi Ltd , 株式会社日立製作所
发明人： IWATA YUTAKA , YUNOKI MASAICHI , ISHII YOSHIHIKO , FUSHIMI ATSUSHI , OCHI HITOSHI
IPC分类号： G21C17/00
摘要： PROBLEM TO BE SOLVED: To effectively inhibit a reactor water temperature changing rate from becoming excessive owing to a moderator temperature coefficient being in a positive state, and the like, as to nuclear reactor output control. SOLUTION: The reactor water temperature changing rate is calculated from detected reactor water temperatures by a temperature changing rate calculator 22. A neutron flux limit value is calculated by a neutron flux limit value calculator 27 from the changing rate at a certain time, a reactor water temperature changing rate limit value previously set as an upper limit value on the changing rate, and neutron flux detected a definite time period before a certain time point. A control rod 4 is put to insertion on condition that the neutron flux is equal to or more than the flux limit value. COPYRIGHT: (C)2005,JPO&NCIPI
摘要翻译：待解决的问题：为了有效地抑制反应堆水温变化率由于调节剂温度系数处于正状态而变得过度等，关于核反应堆输出控制。解决方案：通过温度变化率计算器22从检测的反应器水温度计算反应器水温变化率。中子通量极限值由中子通量极限值计算器27根据特定时间的变化率计算，预先设定为变化率的上限值的反应堆水温度变化率极限值，并且在一定时间点之前检测到确定的时间段的中子通量。在中子通量等于或大于通量极限值的条件下，将控制棒4插入。版权所有（C）2005，JPO＆NCIPI

5. 发明专利

JPH04320996A OPERATION PLANNING METHOD OF NUCLEAR POWER PLANT AND REACTOR AND ITS PLANNING DEVICE 失效
公开(公告)号：JPH04320996A
公开(公告)日：1992-11-11
申请号：JP8851291
申请日：1991-04-19
申请人： HITACHI LTD , HITACHI ENG CO LTD
发明人： KOYAMA JUNICHI , MARUYAMA HIROMI , ISHII YOSHIHIKO , SHIMOJU TAKANORI , NAKAMURA MITSUYA , YUNOKI MASAICHI
IPC分类号： G21C17/00
摘要： PURPOSE:To exactly predict incore power distribution by separating the neutron energy in each core region into plural groups, rearranging the calculated nuclear constants in assemblies using a specific equation for averaging values concerning the average burnup in regions to obtain the ratio between regional average neutron fluxes in the first group and the second group and obtaining fission cross section area. CONSTITUTION:Neutron energy in each reactor region is separated into plural groups. The ratio of regional average neutron fluxes phii and phij between a group i and another group j is calculated with an equation for averaging concerning a regional average burnup E to be a parameter > (where > is history spectrum) and nuclear constants in assemblies are rearranged. Using this rearranged nuclear constants calculated, the fission cross section area is obtained and thus core power distribution is exactly predicted.

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