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1. 发明专利

JP2006275638A Method of processing spent fuel 有权
标题翻译：处理燃料燃料的方法
公开(公告)号：JP2006275638A
公开(公告)日：2006-10-12
申请号：JP2005092506
申请日：2005-03-28
申请人： Hitachi Ltd , 株式会社日立製作所
发明人： YAMASHITA JUNICHI , SASAHIRA AKIRA , KAWAMURA FUMIO , FUKAZAWA TETSUO , HOSHINO KUNIYOSHI , IINO KENJI
IPC分类号： G21C19/44
CPC分类号： Y02W30/882
摘要： PROBLEM TO BE SOLVED: To provide a method of processing spent fuel capable of simplifying a reprocessing facility for spent fuel of thermal neutron reactor and attaining a reduction of facility size and low cost. SOLUTION: Spent fuel exhausted from a nuclear power station (thermal reactor station) is sent to a volume reduction facility for reducing the volume and weight of the spent fuel by removing uranium. By removing most part of uranium, the volume reduction of the spent fuel is attained. The reduced spent fuel is stored as need arises and sent to a reprocessing facility for spent fuel of fast neutron reactor. Uranium and plutonium are extracted and fabricated to fast neutron reactor fuel. COPYRIGHT: (C)2007,JPO&INPIT
摘要翻译：要解决的问题：提供一种处理乏燃料的方法，其能够简化热中子反应堆的乏燃料的后处理设备，并且实现设备尺寸的减小和低成本。解决方案：从核电站（热反应站）排出的废油被运送到减容设备，通过清除铀来减少乏燃料的体积和重量。通过去除大部分铀，实现了乏燃料的体积减少。减少的乏燃料根据需要进行储存，并送到快中子反应堆乏燃料的后处理设备。铀和钚被提取并制成快中子反应堆燃料。版权所有（C）2007，JPO＆INPIT

2. 发明专利

JP2003075575A Boiling water reactor and operation method thereof 审中-公开
标题翻译：锅炉水反应器及其操作方法
公开(公告)号：JP2003075575A
公开(公告)日：2003-03-12
申请号：JP2001267809
申请日：2001-09-04
申请人： Hitachi Ltd , 株式会社日立製作所
发明人： FUJIMURA KOJI , OTSUKA MASAYA , YAMASHITA JUNICHI
IPC分类号： G21C7/00 , G21C7/04 , G21C7/27 , G21C7/32 , G21C15/28
CPC分类号： Y02E30/31 , Y02E30/39
摘要： PROBLEM TO BE SOLVED: To realize an operation method of a boiling water reactor having a super long life reactor core slow in response to a transient event through an operation period while suppressing the degree of excessive reaction.
SOLUTION: In the case of 100% heavy water, the absolute value of void reactivity in an initial state of combustion is as small as about 0.55 $, but the void reactivity is transferred to positive side by the accumulation of
239 Pu generated by neutron capture reaction of
238 U or nuclear fission product according to combustion. Therefore, light water is mixed to the heavy water according to the increase in number of operation years, and its mixing ratio is gradually increased, whereby the neutron spectrum is softened to suppress the increase in positive void reactivity. The light water mixing ratio in coolant is set to 4% in the number of operation years ranging from 0 to 4, 12.5% from 4 to 8, 24% from 8 to 12, 40% from 12 to 16, and 70% from 16 to 20. Accordingly, the void reactivity can be kept at 1 $ or less throughout the operation period.
COPYRIGHT: (C)2003,JPO
摘要翻译：要解决的问题：为了实现具有超长寿命反应堆核心的沸水反应堆的操作方法，其响应于通过操作周期的瞬时事件而缓慢，同时抑制过度反应的程度。解决方案：在100％重水的情况下，在初始燃烧状态下的空隙反应性的绝对值小至约0.55 $，但是空隙反应性通过由根据燃烧，中子俘获反应<238> U或核裂变产物。因此，根据操作年限的增加，将轻水与重水混合，其混合比逐渐增加，中子光谱软化以抑制正空隙反应性的增加。冷水中的轻水混合比为0〜4，12.5％为4〜8，24％为8〜12，40％为12〜16，70％为16 因此，在整个操作期间，空隙反应性可以保持在1美元以下。

3. 发明专利

JPH10288687A FUEL ASSEMBLY 失效
公开(公告)号：JPH10288687A
公开(公告)日：1998-10-27
申请号：JP1852598
申请日：1998-01-30
申请人： HITACHI LTD
发明人： KOYAMA JUNICHI , AOYAMA TADAO , NISHIDA KOJI , YAMASHITA JUNICHI
IPC分类号： G21C3/326 , G21C3/328
摘要： PROBLEM TO BE SOLVED: To provide a fuel assembly for improving a thermal margin on operation, especially a marginal output by considering the distribution of the flow of a cooling material and that of thermal output in a fuel assembly with a short fuel rod. SOLUTION: A short fuel rod 3 is not arranged in a corner region 6 in three rows and three columns and each short fuel rod 3 is arranged at each side of the outermost periphery. Gd fuel rods (a flammable toxic fuel rod containing both uranium dioxide and a flammable toxic substance) 4 are arranged at an area other than the outermost periphery, and more than half of them are not adjacent to the short fuel rod 3. The amount of the flammable toxic substance contained in a polygonal region 10 with each center of the short fuel rod 3 being arranged at the outermost layer as a vertex is smaller than that contained in an area other than the region 10 in a cross section surface at the upper side of the upper edge of the short fuel rod 3.

4. 发明专利

JPH09105792A INITIAL LOADING REACTOR CORE AND FUEL ASSEMBLY 失效
公开(公告)号：JPH09105792A
公开(公告)日：1997-04-22
申请号：JP26294095
申请日：1995-10-11
申请人： HITACHI LTD
发明人： HAIKAWA KATSUMASA , YAMANAKA AKIHIRO , KANDA AKIKO , AOYAMA TADAO , YUJI YOKO , YAMASHITA JUNICHI
IPC分类号： G21C5/12 , G21C3/32 , G21C3/326 , G21C3/328 , G21C3/62 , G21C5/00 , G21C5/02 , G21C7/113
摘要： PROBLEM TO BE SOLVED: To provide an initial loading reactor core enhanced in average enrichment in order to increase burn-up in which surplus reactivity can be properly suppressed while ensuring thermal tolerance, and the fuel economical efficiency can be improved, and a fuel assembly used therefor. SOLUTION: Unit loading patterns are arranged in a high output area 1 having a high output in the center part within a core. The unit loading pattern is formed by providing one low enrichment fuel 8, two high enrichment fuels 9, and one high enrichment fuel 10, and surrounding the circumference of this fuel assembly with four cross control rods.

5. 发明专利

JPH07244182A FUEL ASSEMBLY AND READER CORE 失效
公开(公告)号：JPH07244182A
公开(公告)日：1995-09-19
申请号：JP3809994
申请日：1994-03-09
申请人： HITACHI LTD
发明人： MASUMI RIYOUJI , AOYAMA TADAO , YAMASHITA JUNICHI
IPC分类号： G21C3/328 , G21C3/62 , G21F9/00
摘要： PURPOSE:To provide a fuel assembly and reactor core capable of improving survival rate of fission material and improving the annihilation rate of transuranium elements. CONSTITUTION:A fuel assembly 2 is constituted by bundling fuel rods 3 filled with MOX fuel of natural uranium enriched with transuranium elements and covering with a channel box 21 of Zircaloy. Between the adjacent fuel assemblies 2, a cross shape control rod 6 bundled with absorption rod 61 including boron carbide is inserted. The enrichment of fission plutonium is 11wt.% and that of transuranium elements is 5wt.%. The number of fuel rods is 256 and are arranged in 16X16 array. Water to fuel volume ratio is ca. 2 and H/HM ratio of the fuel assembly 2 is 3 in the case the average void fraction during operation is 40%.

6. 发明专利

JPH0636045B2 失效
公开(公告)号：JPH0636045B2
公开(公告)日：1994-05-11
申请号：JP16797286
申请日：1986-07-18
申请人： HITACHI LTD
发明人： OZAWA MICHIHIRO , NAKAMURA MITSUYA , MOCHIDA TAKAAKI , YAMASHITA JUNICHI
IPC分类号： G21C3/326 , G21C3/32 , G21C3/328

7. 发明专利

JPH065316B2 失效
公开(公告)号：JPH065316B2
公开(公告)日：1994-01-19
申请号：JP22603786
申请日：1986-09-26
申请人： HITACHI LTD
发明人： HAIKAWA KATSUMASA , NAKAMURA MITSUYA , YAMASHITA JUNICHI
IPC分类号： G21C3/326 , G21C3/32

8. 发明专利

JPH05188168A FUEL ASSEMBLY FOR BOILING WATER REACTOR 失效
公开(公告)号：JPH05188168A
公开(公告)日：1993-07-30
申请号：JP493492
申请日：1992-01-14
申请人： HITACHI LTD
发明人： BESSHO TAISUKE , YAMASHITA JUNICHI , UTSUNO HIDEAKI
IPC分类号： G21C3/328
摘要： PURPOSE:To enhance the average takeout burnup as much as possible, to achieve the high burnup and to clear the thermal limit value such as the maximum linear output density when restriction is imposed on the maximum enrichment of uranium. CONSTITUTION:The uranium enrichments of twelve fuel rods 21 and 22 located at the four corners of a fuel assembly and fuel rods 20 other than fuel rods 23 containing combustible poisonous substance are made to be the maximum value uniformly in the fuel assembly. The uranium enrichments of the other fuel rods 21, 22 and 23 are made to be smaller than the maximum value in this constitution. Of the total number of the fuel rods 23 containing burnable poisonous substance, 1/2 or more fuel rods are made to face a water rod. Thus, the high burnup is achieved, and the thermal limit value can be cleared.

9. 发明专利

JPH04290989A FUEL ASSEMBLY 失效
公开(公告)号：JPH04290989A
公开(公告)日：1992-10-15
申请号：JP5436591
申请日：1991-03-19
申请人： HITACHI LTD
发明人： SONEDA HIDEO , YAMASHITA JUNICHI , MOCHIDA TAKAAKI
IPC分类号： G21C3/328
摘要： PURPOSE:To obtain a fuel assembly in which fuel rods by which sufficient control rod value for satisfying the reactor shutdown margin of MOx fuel whose nuclear fission material is plutonium or of high-enrichment uranium fuel for a high burnup can be obtained, gadolinia(Gd) rods, and water rods are arranged. CONSTITUTION:A region A consisting of water rods 4, 4a, and fuel rods 3, 3a 80% or more of which contain burnable poison material, and a region B consisting of a large number of fuel rods not including burnable poison material are provided; and the region A is provided so as to be away from the outer circumference of the fuel assembly 1 more than 3 layers. Since the average thermal neutron bundle in the region B can be significantly increased as compared with that in the region A, an effect for obtaining a control rod value satisfying the reactor shutdown margin can be achieved.

10. 发明专利

JPH0450796A FUEL ASSEMBLY AND REACTOR CORE 失效
公开(公告)号：JPH0450796A
公开(公告)日：1992-02-19
申请号：JP15976390
申请日：1990-06-20
申请人： HITACHI LTD
发明人： SONEDA HIDEO , YAMASHITA JUNICHI , NISHIMURA AKIRA , MOCHIDA TAKAAKI
IPC分类号： G21C3/328
摘要： PURPOSE:To decrease the output peaking in the outer peripheral part of the fuel assembly by increasing the total cross sectional area of channel fasteners and a water rod existing in the region on the side opposite therefrom and disposing the greater part of gadolinia fuel rods in this region. CONSTITUTION:The area of the water rod 300 contained in the region ABD is made larger than the water rod area contained in the region BCD and the number of the gadolinia fuel G to be disposed in the region ABD including the region on a diagonal line B is made larger than the number of the fuel G to be disposed in the region BCD. Further, among 12 pieces of the fuel rods in positions (a) to (l) adjacent to the water rod 300, 4 pieces of the fuel rods G are disposed in the positions (a) to (g) facing the sides AD, AB and the fuel rods G are not disposed in the positions (h) to (l). Then, the region BCD of the low average degree of Pu enrichment is disposed to face the control rods 500 to obtain high reactivity with the water of a wide water gap. The high reactivity is obtd. by increasing the average degree of Pu enrichment in the region ABD which faces the narrow water gap and where moderators are apt to be deficient. The output thereof is, therefore, averaged and the output peaking is decreased.

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