کد مقاله کد نشریه سال انتشار مقاله انگلیسی نسخه تمام متن
1728493 1521134 2014 13 صفحه PDF دانلود رایگان
عنوان انگلیسی مقاله ISI
Neutronic analysis of the Geological Survey TRIGA Reactor
موضوعات مرتبط
مهندسی و علوم پایه مهندسی انرژی مهندسی انرژی و فناوری های برق
پیش نمایش صفحه اول مقاله
Neutronic analysis of the Geological Survey TRIGA Reactor
چکیده انگلیسی


• We develop a detailed MCNP model of the Geological Survey TRIGA Reactor.
• We present a simplified approach to considering burnup.
• The model is validated against available reactor data.
• We present evidence of inaccuracies in the ENDF B/VII zirconium libraries.

The United States Geological Survey TRIGA Reactor (GSTR) is a 1 MW reactor located in Lakewood, Colorado. In support of the GSTR’s relicensing efforts, this project developed and validated a Monte Carlo N-Particle Version 5 (MCNP5) model of the GSTR reactor. The model provided estimates of the excess reactivity, power distribution and the fuel temperature, water temperature, void, and power reactivity coefficients for the current and limiting core. The MCNP5 model predicts a limiting core excess reactivity of $6.48 with a peak rod power of 22.2 kW. The fuel and void reactivity coefficients for the limiting core are strongly negative, and the core water reactivity coefficient is slightly positive, consistent with other TRIGA analyses. The average fuel temperature reactivity coefficient of the full power limiting core is −0.0135 $/K while the average core void coefficient is −0.069 $/K from 0% to 20% void. The core water temperature reactivity coefficient is +0.012 $/K.

ناشر
Database: Elsevier - ScienceDirect (ساینس دایرکت)
Journal: Annals of Nuclear Energy - Volume 64, February 2014, Pages 122–134
نویسندگان
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