Journal
NUCLEAR ENGINEERING AND DESIGN
Volume 283, Issue -, Pages 155-161Publisher
ELSEVIER SCIENCE SA
DOI: 10.1016/j.nucengdes.2014.03.012
Keywords
-
Categories
Funding
- Slovenian Research agency
- bilateral CEA/Ministry of higher education, science and technology of Slovenia [BI-FR/CEA/10-12-005, 5100-3/2012-14]
Ask authors/readers for more resources
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.
Authors
I am an author on this paper
Click your name to claim this paper and add it to your profile.
Reviews
Recommended
No Data Available