Results 131 to 140 of about 449 (175)

BAEC TRIGA research reactor: 35 years' experience

International Journal of Nuclear Energy Science and Technology, 2022
Abdullah Al Mahmud
exaly   +2 more sources

FiR1 TRIGA research reactor decommissioning project

2017
FiR1 is a 250 kW TRIGA Mark II type open pool reactor from General Atomics. It has been in operation for education, research, BNCT treatments and isotope production in Finland for years 1962-2015 and is planned to be decommissioned in following few years. Overall the reactor has been in use for around 11500 MWh. Radioactive waste will consist mainly of
Räty Antti, Airila Markus, Kotiluoto Petri, Auterinen Iiro, Calonius Kim, Vilkamo Olli, Juutilainen Pauli, Kekki Tommi   +7 more
openaire   +4 more sources

Optimum burnup of BAEC TRIGA research reactor

Annals of Nuclear Energy, 2013
Abstract The TRIGA Mark II research reactor of BAEC (Bangladesh Atomic Energy Commission) has been operating since 1986 without any reshuffling or reloading yet. Optimum fuel burnup strategy has been investigated for the present BAEC TRIGA core, where three out-to-in loading schemes have been inspected in terms of core life extension, burnup economy ...
Zoairia Idris Lyric, Mohammad Sayem Mahmood, Mohammad Abdul Motalab, Jahirul Haque Khan   +3 more
openaire   +1 more source

Determination of the irradiation field at the research reactor TRIGA Mainz for BNCT

Applied Radiation and Isotopes, 2009
For the application of the BNCT for the excorporal treatment of organs at the TRIGA Mainz, the basic characteristics of the radiation field in the thermal column as beam geometry, neutron and gamma ray energies, angular distributions, neutron flux, as well as absorbed gamma and neutron doses must be determined in a reproducible way.
C, Duvinage, S, Nagels, G, Hampel, J V, Kratz, A L, Aguilar, S, Minouchehr, G, Otto, H, Schmidberger, C, Schütz, L, Vogtländer, B, Wortmann   +10 more
openaire   +3 more sources

Fuel burnup analysis for the Moroccan TRIGA research reactor

Annals of Nuclear Energy, 2013
Abstract The fundamental advantage and main reason to use Monte Carlo methods for burnup calculations is the possibility to generate extremely accurate burnup dependent one group cross-sections and neutron fluxes for arbitrary core and fuel geometries.
B. El Bakkari, T. El Bardouni, B. Nacir, C. El Younoussi, Y. Boulaich, H. Boukhal, M. Zoubair   +6 more
openaire   +1 more source

The development of TM2-RIA code for TRIGA type research reactors

Annals of Nuclear Energy, 2020
Abstract This work presents the development of indigenous code TM2-RIA for steady-state and transient analyses of TRIGA type research reactor at Istanbul Technical University Energy Institute. The 2-dimensional code adapts piecewise constant function for solving point kinetics equation linked with thermal–hydraulic equations for cylindrical fuel type.
Mohammad Amer Allaf, Senem Şentürk Lüle, Üner Çolak   +2 more
openaire   +1 more source

Measurements of epithermal neutron properties of ITU Triga Mark II research reactor

Applied Radiation and Isotopes, 2022
The k0 standardization method is one of the most commonly used neutron activation analyses to determine the concentrations of elements in the sample. To perform this method, it is required to know the neutron spectrum parameters such as epithermal neutron flux shape factor (α) and thermal to epithermal neutron flux ratio (f). In this study, the α and f
Neslihan Koyuncu, Onur Erbay, İskender Atilla Reyhancan   +2 more
openaire   +2 more sources

Reactor physics evaluation of the TRIGA LEU fuel in the 20 MW NIST research reactor

Nuclear Engineering and Design, 2020
Abstract This paper performs a neutronics evaluation of the General Atomics UZrHx low enriched uranium fuel – TRIGA fuel – in the National Bureau of Standards Reactor (NBSR) at the National Institute of Standards and Technology (NIST). The objective of this study is to examine the accountability and sustainability of the TRIGA fuel on neutronics ...
Kyle A. Britton, Zeyun Wu
openaire   +1 more source

Assessment of a RELAP5 model for the IPR-R1 TRIGA research reactor

Annals of Nuclear Energy, 2010
Abstract RELAP5 code was developed at the Idaho National Environmental and Engineering Laboratory and it is widely used for thermal hydraulic studies of commercial nuclear power plants and, currently, it has been also applied for thermal hydraulic analysis of nuclear research systems with good predictions.
Patrícia A.L. Reis, Antonella L. Costa, Cláubia Pereira, Maria A.F. Veloso, Amir Z. Mesquita, Humberto V. Soares, Graiciany de P. Barros   +6 more
openaire   +1 more source

Minimizing radiation exposure for the reactor staff during the dismantling of a TRIGA research reactor

Kerntechnik, 2006
Abstract An experimental method for the determination of the long-term activation of concrete shielding has been performed for two TRIGA research reactors in Ljubljana, Slovenia and in Vienna, Austria. The activity of concrete was studied on concrete samples taken directly from the external shielding of the reactor body with consecutive ...
openaire   +1 more source