Using TRIGA Mark II research reactor for irradiation with thermal neutrons
Using TRIGA Mark II research reactor for irradiation with thermal neutrons
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DOI：
10.1016/j.nucengdes.2014.03.012
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发表时间：
2015-03-01
影响因子：
1.7
通讯作者：
Snoj, Luka
中科院分区：
文献类型：
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作者：
Kolsek, Aljaz;Radulovic, Vladimir;Snoj, Luka
最近，在JSI TRIGA Mark II反应堆上进行了一系列的试验辐照，用于裂变径迹-热电离质谱（FT-TIMS）方法，该方法需要热化良好的中子谱来进行样品辐照。为此，利用蒙特卡罗n粒子输运码（MCNP5）在计算上支持TRIGA模型内辐照装置的设计，并通过计算主要堆芯外辐照设施内的中子通量来支持实际测量。在热柱内设计和优化了充满重水的辐照装置，并在高架穿孔内放置了额外的缓和剂。该装置的使用将热中子通量与热柱端口内超热中子和快中子通量之和的比率提高了390%，并在20 h的辐照时间内达到了10（15）个中子/cm(2)的期望热中子通量。(C) 2014 Elsevier B.V.。
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.