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首页> 外文期刊>Energy Conversion & Management >Burning and/or transmutation of transuraniums discharged from PWR-UO_2 spent fuel and power flattening along the operation period in the force free helical reactor
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Burning and/or transmutation of transuraniums discharged from PWR-UO_2 spent fuel and power flattening along the operation period in the force free helical reactor

机译：从PWR-UO_2乏燃料中排出的超铀的燃烧和/或trans变在无力螺旋反应堆中沿运行期进行平展

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The burning and/or transmutation (B/T) of transuraniums (TRUs) in the force free helical reactor (FFHR), which is a demo relevant helical type D-T fusion reactor, has been investigated for an operation period (OP) of up to ten years by 75% plant factor (η) under a neutron wall load (P) of 1.5 MW/m~2. The transmutation zone (TZ), containing the mixture of TRU nuclides discharged from uranium fueled pressurized water reactor spent fuel, has been located in the blanket of the FFHR to incinerate and/or transmute the TRUs effectively. The TRU mixture, including minor actinides (MAs) and Pu isotopes, has been spherically prepared and cladded with SiC to prevent the TRU nuclides from contacting the coolant and the fission products from contaminating the coolant. Helium has been used for the nuclear heat transfer in the TZ. The effect of the Pu volume fraction in the TRU mixture on the B/T has also been investigated for acquiring a quasi-constant fission power generation along the OP. The neutron multiplication coefficient (k_(eff), relating to the fission rate (R_F), is less than 0.9 in all investigated cases during the OP. The tritium breeding ratio value is greater than 1.1 for all investigated cases so that tritium self-sufficiency is maintained for the (D,T) fusion driver. During the OP, in the case of a Pu fraction of 18.1%, the peak to average fission power density ratio (Γ) value is about 1.09, and the R_F is also quasi-constant (about 0.95) along the OP. At the end of the OP, the effective half lives of ~(237)Np, ~(239)Pu, ~(241)Pu, ~(241)Am and ~(243)Am decrease to about 5, 6.5, 7.5, 10 and 7 years, respectively, and the net transmutation fractions for the whole TRUs and MAs are obtained as 46% and 69%, respectively. These consequences show that the blanket accomplishes the B/T of the TRUs effectively, and in the case of a Pu fraction of 18.1%, the TZ has a good flat fission power density profile and a quasi-invariable R_F along the OP.
机译：已研究了演示相关的螺旋型DT聚变反应堆无力螺旋反应堆（FFHR）中铀（TRU）的燃烧和/或trans变（B / T），其运行期（OP）最高为在中子壁负荷（P）为1.5 MW / m〜2的条件下，通过75％的工厂因子（η）来计算十年。 containing变区（TZ）包含从FFHR覆盖层中排出的铀浓缩加压水反应堆乏燃料排放的TRU核素混合物，可以有效地焚化和/或转化TRU。 TRU混合物（包括次act系元素（MAs）和Pu同位素）已进行球形制备，并用SiC包覆，以防止TRU核素接触冷却剂和裂变产物污染冷却剂。氦气已用于TZ中的核热传递。为了获得沿OP的准恒定裂变发电，还研究了TRU混合物中Pu体积分数对B / T的影响。在OP中所有被调查的案例中，与裂变率（R_F）有关的中子倍增系数（k_（eff）小于0.9。在所有被调查的案例中，tri的繁殖率值均大于1.1，因此tri的自给自足在OP中，当Pu分数为18.1％时，峰均裂变功率密度比（Γ）值约为1.09，R_F也近似为沿OP恒定（约0.95）。在OP结束时，〜（237）Np，〜（239）Pu，〜（241）Pu，〜（241）Am和〜（243）Am的有效半衰期分别降低到大约5年，6.5年，7.5年，7.5年，10年和7年，整个TRU和MA的净trans变分数分别为46％和69％，这些结果表明毯子达到了B / T。 TRU有效，并且在Pu率为18.1％的情况下，TZ具有良好的平坦裂变功率密度分布，并且沿OP的准不变R_F不变。

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