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首页> 外文期刊>Annals of nuclear energy >Power flattening in Prometheus breeder reactor using nuclear fuel and waste actinide
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Power flattening in Prometheus breeder reactor using nuclear fuel and waste actinide

机译:使用核燃料和waste系元素在普罗米修斯增殖反应堆中进行功率扁平化

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In this study, the possibility of power flattening of the DT driven blanket in the Prometheus-H (Heavy ion) breeder reactor cooled with helium and fueled with different mixed fuels and nuclear waste actinide is investigated. The research has been performed individually for each mixed fuels, namely, UC-ThC, UO_2-ThO_2, UC-C, UO_2-C and ~(244)CmO_2-UO_2, with various mixture fractions. The mixed fuels with variable fractions of the compounds are spherically prepared, and cladded with SiC to prevent fission products from contaminating coolant in the blanket. The fuel spheres are replaced in the blanket as 10 rows in radial direction. Fractions of the uranium and curium compounds in each mixed fuel are linearly increased from the first to last row of the FFB (fissile fuel breeding) zone to obtain quasi-constant FPD (fission power density) profiles. Calculations of neutronic data per DT fusion neutron have been performed by using SCALE 4.4a Code. The blanket fueled with mixed ~(244)CmO_2(10%)-UO_2 has maximum M (energy multiplication ratio) being one of main parameters in a fusion-fission hybrid reactor, while total FFBR (fissile fuel breeding ratio) reaches 0.212 in the case of mixed UC(70%)-ThC. TBR (tritium breeding ratio) values are greater than 1.05 in all investigated cases so that tritium self-sufficiency is maintained for (D,T) fusion driver. Neutron leakage out of the blanket is quite low. The spatial non-uniform fission energy density, defined with the help of peak-to-average fission power density ratio, F, is reduced from about 1.4 to 1.05, and quasi-uniform FPD profiles are obtained by using the method of linearly increased mixture fraction, which means excellent power flattening. Calculations show that in all investigated cases, the breeder reactor has high neutronic performance and can produce substantial electricity in situ, fissile fuel and tritium required for (D,T) fusion reaction, and the method of linearly increased mixture fraction can supply the quasi-uniform FPD profiles.
机译:在这项研究中,研究了用氦气冷却并用不同的混合燃料和核废act系元素作为燃料的普罗米修斯-H(重离子)增殖反应堆中DT驱动毯的功率变平的可能性。已经对每种混合燃料,即各种混合分数的UC-ThC,UO_2-ThO_2,UC-C,UO_2-C和〜(244)CmO_2-UO_2进行了单独研究。将具有可变比例化合物的混合燃料制成球形,并用SiC包覆,以防止裂变产物污染橡皮布中的冷却剂。燃料层在橡皮布中沿径向方向替换为10行。从FFB(易裂变燃料育种)区的第一行到最后一行,每种混合燃料中铀和cur化合物的分数线性增加,以获得准恒定的FPD(裂变功率密度)曲线。每个DT聚变中子的中子数据的计算已使用SCALE 4.4a代码进行。混合〜(244)CmO_2(10%)-UO_2混合的毯子具有最大的M(能量倍增比)是聚变裂变混合反应堆的主要参数之一,而总FFBR(可裂变燃料的繁殖率)在核裂变混合堆中达到0.212。混合UC(70%)-ThC的情况。在所有调查的案例中,TBR(tri繁殖率)值均大于1.05,因此对于(D,T)融合驱动器,tri保持了自给自足的状态。中子从橡皮布中泄漏的可能性非常低。借助峰均裂变功率密度比F定义的空间不均匀裂变能量密度从约1.4降低到1.05,并通过使用线性增加混合的方法获得了准均匀FPD分布图分数,这意味着出色的功率平坦度。计算表明,在所有调查的情况下,增殖反应堆均具有较高的中子性能,可产生大量原位电,(D,T)聚变反应所需的易裂变燃料和tri,并且线性增加混合比的方法可提供准电。统一的FPD轮廓。

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