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Monte Carlo analysis of helium Production in the ITER shielding blanket module

机译:ITER屏蔽层模块中氦气产生的蒙特卡洛分析

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In order to examine the shielding performances of the inboard blanket module in the International Thermonuc1ear Experimental Reactor (ITER), shielding calculations have been carried out using a three-dimensional Monte Carlo method. The impact of radiation streaming through the front access holes and gaps between adjacent blanket modules on the helium gas production in the branch pipe weld locations and back plate have been estimated. The three-dimensional model represents an l8" sector of the overall torus region and includes the vacuum vessel, inboard blanket and back plate, plasma region, and outboard reflecting medium. And it includes the l m high inboard mid-plane module and the 20 mm wide gaps between adjacent modules. From the calculated results for the reference design, it has been found that the helium production at the plug of the branch pipe is four to five times higher than the design goal of l appm for a neutron fluence of 0.9 MW a m-- 2 at the inboard mid-plane first wall. Also, it has been found that the helium production at the back plate behind the horizontal gap is about three times higher than the design goal. In the reference design, the stainless steel (SS)fH,O composition in the blanket module is 80:20/100. Shielding calculations also have been carried out for the SS:H_2O composition of 70f30, 60:40, 50:50 and 40:60/100. From the eva1uated results for their design, it has been found that the dependence of helium production on the SS:H_2O composition in the blanket module is small at the branch pipe. Altering the steel--water ratio to reduce the amount of steel and increasing the thickness by > l70 mm will reduce helium production to satisfy the design goal and not have a significant impact on weight limitations imposed by remote maintenance handling limitations. Also based on the calculated results, about 200 mm thick shields such as a key structure in the vertica1 gap are suggested to be installed in the horizontal gap as well to reduce the helium production at the back p1ate and to satisfy the design goal.
机译:为了检查国际热核实验反应堆(ITER)中内侧毯子模块的屏蔽性能,已使用三维蒙特卡洛方法进行了屏蔽计算。已经估计了通过前检修孔和相邻橡皮布模块之间的间隙流过的辐射对分支管焊接位置和后板中产生的氦气的影响。三维模型代表整个环面区域的18英寸扇区,包括真空容器,内侧橡皮布和背板,等离子体区域以及外侧反射介质。它包括lm高内侧中平面模块和20 mm从参考设计的计算结果发现,对于中子注量为0.9 MW,支管塞处的氦气产量比l appm的设计目标高出四到五倍。在内侧中平面第一壁的m–2处,并且还发现水平间隙后面的背板上的氦气产量比设计目标高出大约三倍。覆盖模块中的(SS)fH,O组成为80:20/100。还对70:30、60:40、50:50和40:60/100的SS:H_2O组成进行了屏蔽计算。评估了他们的设计结果,结果发现毯状组件中的SS:H_2O成分产生的氦气在分支管上的依赖性很小。更改钢水比以减少钢量并增加厚度> 170毫米将减少氦气产量以满足设计目标,并且不会对因远程维护处理限制而造成的重量限制产生重大影响。同样根据计算结果,建议在水平缝隙中安装约200 mm厚的屏蔽层,例如在垂直缝隙中形成关键结构,以减少后部氦气的产生并满足设计目标。

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