Stankunas Gediminas, Cufar Aljaz, Tidikas Andrius, Batistoni Paola
Laboratory of Nuclear Installation Safety, Lithuanian Energy Institute, Breslaujos str. 3, Kaunas, Lithuania.
Jozef Stefan Institute, Department of Reactor Physics, Jamova 39, Ljubljana, Slovenia.
Radiat Prot Dosimetry. 2018 Aug 1;180(1-4):125-128. doi: 10.1093/rpd/ncx262.
Irradiations with 14 MeV fusion neutrons are planned at Joint European Torus (JET) in DT operations with the objective to validate the calculation of the activation of structural materials in functional materials expected in ITER and fusion plants. This study describes the activation and dose rate calculations performed for materials irradiated throughout the DT plasma operation during which the samples of real fusion materials are exposed to 14 MeV neutrons inside the JET vacuum vessel. Preparatory activities are in progress during the current DD operations with dosimetry foils to measure the local neutron fluence and spectrum at the sample irradiation position. The materials included those used in the manufacturing of the main in-vessel components, such as ITER-grade W, Be, CuCrZr, 316 L(N) and the functional materials used in diagnostics and heating systems. The neutron-induced activities and dose rates at shutdown were calculated by the FISPACT code, using the neutron fluxes and spectra that were provided by the preceding MCNP neutron transport calculations.
计划在欧洲联合环形反应堆(JET)的氘氚运行中使用14兆电子伏聚变中子进行辐照,目的是验证国际热核聚变实验堆(ITER)和聚变电厂中预期的功能材料中结构材料活化的计算。本研究描述了在氘氚等离子体运行期间对材料进行的活化和剂量率计算,在此期间,实际聚变材料的样品在JET真空容器内暴露于14兆电子伏中子。在当前的氘氘运行期间,正在进行准备活动,使用剂量测定箔来测量样品辐照位置的局部中子注量和能谱。这些材料包括用于制造主要内部组件的材料,如ITER级钨、铍、铜铬锆、316L(N)以及诊断和加热系统中使用的功能材料。通过FISPACT代码,利用先前MCNP中子输运计算提供的中子通量和能谱,计算了停机时的中子诱发活度和剂量率。