会员体验
专利管家(专利管理)
工作空间(专利管理)
风险监控(情报监控)
数据分析(专利分析)
侵权分析(诉讼无效)
联系我们
交流群
官方交流:
QQ群: 891211   
微信请扫码    >>>
现在联系顾问~
热词
    • 2. 发明专利
    • OPERATION METHOD FOR BOILING WATER REACTOR
    • JPH07128489A
    • 1995-05-19
    • JP27822793
    • 1993-11-08
    • TOSHIBA CORPTOSHIBA ENGINEERING CO
    • IKEDA ATSUKOKANEKO HIROHISAISHIZUKA HISAO
    • G21C7/27G21D3/00G21D3/12
    • PURPOSE:To improve reactivity by controlling reactivity with fine operation of control rods without lowering load in the beginning and middle of cycle and by performing spectrum shift operation with lowering load and suppressing the rise of linear power density due to the control rod history effects in the end of cycle. CONSTITUTION:In the case where the excess reactivity is gradually increasing in the beginning of cycle, control rods are finely controlled (as denoted with digits in the figures) as (b), (c), in the control rod plant. The pattern control is performed at the time when the core flow reaches a lower limit. If the rise of excess reactivity ends and the control rod pattern (d) in the middle of cycle, then fine control is repeated as (c), (e). If the linear power density exceeds a limitation valve in the case of control rod operation without lowering load in the end of cycle, after waiting the rise of core flow for the total withdrawal of one group of control rods, the load is lowered and the particular control rods are totally withdrawn. For this purpose, the load drop and control rod withdrawing procedure are set according to the measurement in advance.
    • 4. 发明专利
    • BOILING WATER REACTOR
    • JPS63284492A
    • 1988-11-21
    • JP11891087
    • 1987-05-18
    • TOSHIBA CORP
    • EGUCHI YUMIKOIKEDA ATSUKO
    • G21C3/328G21C3/30G21C5/12G21C5/18
    • PURPOSE:To maintain specified excess reactivity and to assure the characteristics of a reactor core by maintaining the rate of enriching plutonium in the uranium plutonium fuel rods disposed in a 1st fuel assembly at the rate smaller than the rate of the 2nd fuel assembly. CONSTITUTION:The reactor core 15 is constituted as, for example, a replacement core with which about 1/3 fuel is to be replaced. The blank parts in the figure of this case indicate the positions of the fuel assemblies 13 and fuel assemblies 14 which are burned by >=1 cycle. The parts 1 indicate the positions of the fuel assemblies 13 among the fresh fuel assemblies and the parts 2 indicate the positions of the fuel assemblies 14 among the fresh fuel assemblies. The fuel assembly 13 includes 22 pieces of MOX fuel rods (codes P1, P2) and the rate of enriching the plutonium of P1, P2 are respectively set at 5.0wt.% and 3.0wt.%. Designing of such core which minimizes the burnup change of the excess reactivity by changing the number of the fuel assemblies 13 and the fuel assemblies 14 is enabled when the compsn. of the plutonium and the operation period are determined.
    • 6. 发明专利
    • CORE FOR BOILING WATER REACTOR
    • JPH0943377A
    • 1997-02-14
    • JP19026595
    • 1995-07-26
    • TOSHIBA CORP
    • IKEDA ATSUKOKUROKI MASAHIKO
    • G21C5/00G21C5/12
    • PROBLEM TO BE SOLVED: To improve economical efficiency of fuel and freedom degree of core design by loading a high enrichment fuel assembly having the highest mean enrichment and a low mean enrichment fuel assembly in the outermost circumferential position of the core. SOLUTION: An initial loading core 11 is composed of three types of fuel assembly (low enrichment fuel assembly (A) of the lowest mean enrichment, intermediate medium enrichment fuel assembly (B), and high enrichment assembly (C) of the highest mean enrichment) of different mean enrichments. This core 11 is so constituted that three types of fuel assembly A-C are loaded and the fuel assembly C, A are loaded in its outermost circumferential position. After the first cycle is driven in the core 11, the fuel of the second cycle is so arranged that the fuel assembly (C) out of four bodies of fuel assembly surrounding a control rod, which is loaded in the outermost circumference in the first cycle, is rearranged so as to be used as the high enrichment fuel assembly.
    • 7. 发明专利
    • BOILING WATER REACTOR
    • JPS63293493A
    • 1988-11-30
    • JP12800987
    • 1987-05-27
    • TOSHIBA CORP
    • HATTORI SHINJIIKEDA ATSUKO
    • G21C5/12G21C3/30G21C3/328G21C5/18
    • PURPOSE:To enable safe and stable operation by setting the water to fuel ratio of a mixed type fuel assembly at the ratio larger than the water to fuel ratio of an uranium fuel assembly. CONSTITUTION:The water to fuel ratio of the mixed type fuel assembly for a boiling water reactor using uranium fuel and mixed type fuel is set at the ratio larger than the water to fuel ratio of the uranium fuel assembly, by which the neutron flux spectra in the mixed type fuel assembly are equalized to the neutron flux spectra of the uranium fuel assembly. The neutron attenuation effects are equalized as well and the various characteristics such as void coefft., axial output distribution and shut-down margin of reactor of the mixed type fuel assembly are equalized to the same characteristics of the uranium fuel assembly. The good characteristics which compare favorably with the characteristics of the reactor core using only the uranium fuel assembly are, therefore, provided even if the uranium fuel assembly and the mixed type fuel assembly are used in combination. The safe and stable operation is thus enabled.
    • 10. 发明专利
    • JPH05249271A
    • 1993-09-28
    • JP4569792
    • 1992-03-03
    • TOSHIBA CORP
    • KANOU YOSHIJIIKEDA ATSUKO
    • G21C7/08G21C7/26G21C17/00G21D3/04
    • PURPOSE:To always make possible setting of right selection control rods by exactly and quickly alarming a modification time in the case where an operation area is enlarged and it is necessary to modify a selection control rod pattern in accordance with an operation point. CONSTITUTION:Points A-C on a straight line L are within the range of normal rated output operation, for instance, when operation is performed at a point A and two recirculation pumps trip, the thermal output and the flow of a reactor core are lowered down to another point (a) on a curve l1. But, when operation enters an unstable area R0 on the way, a selection control rod is inserted and the thermal output of the reactor core is controlled within the target output range of Pu-P1 for the area R1. In another selection control rd pattern, the thermal output of the reactor core is controlled in the range of Pu-P1 for the area R2. Before reactor start, in the case where input is performed in regard to the areas R1, R2 and when one of two modes 1(2), is selected, an alarm for pressing setting modification is given when the thermal output thereof is lower (higher) than a value indicating another curve l2. Thereby the modification of the selection control rod is quickly performed without any need of human monitoring in a necessary time and proper selection control rod can be set always.