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基于蒙特卡罗方法的JET应用停机剂量率计算的基准测试。

Benchmarking of Monte Carlo based shutdown dose rate calculations for applications to JET.

作者信息

Petrizzi L, Batistoni P, Fischer U, Loughlin M, Pereslavtsev P, Villari R

机构信息

Associazione EURATOM-ENEA sulla Fusione, CR Frascati, CP 65, Frascati, I-00044 Rome, Italy.

出版信息

Radiat Prot Dosimetry. 2005;115(1-4):80-5. doi: 10.1093/rpd/nci183.

Abstract

The calculation of dose rates after shutdown is an important issue for operating nuclear reactors. A validated computational tool is needed for reliable dose rate calculations. In fusion reactors neutrons induce high levels of radioactivity and presumably high doses. The complex geometries of the devices require the use of sophisticated geometry modelling and computational tools for transport calculations. Simple rule of thumb laws do not always apply well. Two computational procedures have been developed recently and applied to fusion machines. Comparisons between the two methods showed some inherent discrepancies when applied to calculation for the ITER while good agreement was found for a 14 MeV point source neutron benchmark experiment. Further benchmarks were considered necessary to investigate in more detail the reasons for the different results in different cases. In this frame the application to the Joint European Torus JET machine has been considered as a useful benchmark exercise. In a first calculational benchmark with a representative D-T irradiation history of JET the two methods differed by no more than 25%. In another, more realistic benchmark exercise, which is the subject of this paper, the real irradiation history of D-T and D-D campaigns conducted at JET in 1997-98 were used to calculate the shut-down doses at different locations, irradiation and decay times. Experimental dose data recorded at JET for the same conditions offer the possibility to check the prediction capability of the calculations and thus show the applicability (and the constraints) of the procedures and data to the rather complex shutdown dose rate analysis of real fusion devices. Calculation results obtained by the two methods are reported below, comparison with experimental results give discrepancies ranging between 2 and 10. The reasons of that can be ascribed to the high uncertainty on the experimental data and the unsatisfactory JET model used in the calculation. A new dedicated JET benchmark experiment will be performed trying to solve these issues.

摘要

停堆后剂量率的计算是运行核反应堆的一个重要问题。需要一个经过验证的计算工具来进行可靠的剂量率计算。在聚变反应堆中,中子会引发高水平的放射性,可能导致高剂量。设备复杂的几何形状要求使用复杂的几何建模和计算工具进行输运计算。简单的经验法则并不总是适用。最近开发了两种计算程序并应用于聚变装置。两种方法的比较表明,在应用于国际热核聚变实验堆(ITER)的计算时存在一些内在差异,而在一个14 MeV点源中子基准实验中发现了良好的一致性。需要进一步的基准测试来更详细地研究不同情况下结果不同的原因。在此框架下,将对欧洲联合环形加速器(JET)的应用视为一次有用的基准测试。在第一次具有JET代表性氘 - 氚辐照历史的计算基准测试中,两种方法的差异不超过25%。在另一次更实际的基准测试中,也就是本文的主题,使用了1997 - 1998年在JET进行的氘 - 氚和氘 - 氘运行的实际辐照历史来计算不同位置、辐照和衰变时间的停堆剂量。在相同条件下在JET记录的实验剂量数据提供了检验计算预测能力的可能性,从而展示了这些程序和数据在实际聚变装置相当复杂的停堆剂量率分析中的适用性(和局限性)。下面报告了两种方法获得的计算结果,与实验结果的比较给出了2到10之间的差异。其原因可归因于实验数据的高度不确定性以及计算中使用的JET模型不理想。将进行一次新的专门针对JET的基准实验以试图解决这些问题。

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