Experimental and MCNP5 based evaluation of neutron and gamma flux in the irradiation ports of the University of Utah research reactor

Abstract

Neutron and gamma flux environment of various irradiation ports in the University of Utah training, research, isotope production, general atomics reactor were experimentally assessed and fully modeled using the MCNP5 code. The experimental measurements were based on the cadmium ratio in the irradiation ports of the reactor, flux profiling using nickel wire, and gamma dose measurements using thermo luminescence dosimeter. Full 3-D MCNP5 reactor model was developed to obtain the neutron flux distributions of the entire reactor core and to compare it with the measured flux focusing at the irradiation ports. Integration of all these analysis provided the updated comprehensive neutron-gamma flux maps of the existing irradiation facilities of the University of Utah TRIGA reactor

Analisis dan Uji Kinerja Operasi Reaktor Kartini Sebagai Sumber Neutron Fasilitas Eksperimen SAMOP

“…Parameter k 0 dan k masing-masing adalah faktor perlipatan neutron atau tingkat kekritisan reaktor sebelum dan sesudah batang kendali disisipkan. Hasil konfigurasi berdasar simulasi dengan MCNP ini sangat bersesuaian dengan hasil perhitungan pada reaktor sejenis [10][11][12]. Konfigurasi teras sebelum eksperimen uji operasi 100 jam kontinyu, disajikan pada Gambar 1.…”

Characterization of control rod worths and fuel rod power peaking factors in the university of Utah TRIGA Mark I reactor

“…In the past, fea sibil ity stud ies in volv ing power up grade of the UUTR have been con ducted; more spe cif i cally, the con trol rods, cool ing sys tem de sign, and the re quire ments were fully eval u ated [2,3]. More over, neu tron and gamma flux den sity in the ir ra di a tion ports have also been as sessed as de tailed in [4].…”