Monte Carlo calculation of radiation damage in first wall of an experimental hybrid reactor

被引：37

作者：

Sahin, Haci Mehmet ^{[1
]}

机构：

[1] Gazi Univ, Tekn Egitim Fak, Teknikokullar, TR-06503 Ankara, Turkey

来源：

ANNALS OF NUCLEAR ENERGY | 2007年 / 34卷 / 11期

关键词：

D O I：

10.1016/j.anucene.2007.04.011

中图分类号：

TL [原子能技术]; O571 [原子核物理学];

学科分类号：

0827 ; 082701 ;

摘要：

This work was focused on the neutronic calculation of the nuclear parameters (neutron spectrum, displacement per atom (DPA), gas production, tritium breeding ratio (TBR), nuclear heating) for structural materials in the first wall (FW) and fuel clad (made of ferritic/martensitic steels, vanadium alloy, silicon carbide, copper alloy, and stainless steel) of an experimental hybrid reactor using the most current Monte Carlo Neutron-Particle Transport code MCNP5 1.4. Neutronic calculations were performed using a (DT) fusion driver hybrid reactor under a neutron wall loud of 2.25 MW/m(2) by full reactor power for one year. Obtained results were compared with three different data libraries (ENDF/B-V, ENDF/B-VI and CLAW-IV). TBR values in the reactor blanket for all investigated materials became greater than the minimum requirement (TBR > 1.05). Nuclear parameters like DPA, He-production and nuclear heating were considered as radiation damage limits for structural materials, copper alloy (Cu0.5Cr0.3Zr) showed better performance than all investigated materials. (c) 2007 Elsevier Ltd. All rights reserved.

引用

页码：861 / 870

页数：10

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