Using TRIGA Mark II research reactor for irradiation with thermal neutrons

被引：30

作者：

Kolsek, Aljaz ^{[1
]}

Radulovic, Vladimir ^{[1
]}

Trkov, Andrej ^{[1
]}

Snoj, Luka ^{[1
]}

机构：

[1] Jozef Stefan Inst, SI-1000 Ljubljana, Slovenia

来源：

NUCLEAR ENGINEERING AND DESIGN | 2015年 / 283卷

关键词：

FLUX DISTRIBUTION; VALIDATION; MCNP;

D O I：

10.1016/j.nucengdes.2014.03.012

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：

Recently a series of test irradiations was performed at the JSI TRIGA Mark II reactor for the Fission Track-Thermoionization Mass Spectrometry (FT-TIMS) method, which requires a well thermalized neutron spectrum for sample irradiation. For this purpose the Monte Carlo N-Particle Transport Code (MCNP5) was used to computationally support the design of an irradiation device inside the TRIGA model and to support the actual measurements by calculating the neutron fluxes inside the major ex-core irradiation facilities. The irradiation device, filled with heavy water, was designed and optimized inside the Thermal Column and the additional moderation was placed inside the Elevated Piercing Port. The use of the device improves the ratio of thermal neutron flux to the sum of epithermal and fast neutron flux inside the Thermal Column Port by 390% and achieves the desired thermal neutron fluence of 10(15) neutrons/cm(2) in irradiation time of 20 h. (C) 2014 Elsevier B.V. All rights reserved.

引用

页码：155 / 161

页数：7

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