Calculation of fuel burnup and excess reactivity using TRIGLAV code for the BAEC TRIGA research reactor

2020 ◽  
Vol 14 (4) ◽  
pp. 291
Author(s):  
Md. Mizanur Rahman ◽  
Anisur Rahman ◽  
Shafiul Hossain ◽  
P.K. Das ◽  
Md. Ashraf Ali ◽  
...  
Keyword(s):  
Research Reactor ◽  
Fuel Burnup

scholarly journals Fuel burnup analysis for Thai research reactor by using MCNPX computer code

2017 ◽  
Vol 860 ◽  
pp. 012033 ◽  
Author(s):  
S Sangkaew ◽  
T Angwongtrakool ◽  
B Srimok
Keyword(s):  
Research Reactor ◽  
Computer Code ◽  
Fuel Burnup

Validation of the Onsite Used Operational Code Against Burnup Measurement

2016 ◽  
Vol 3 (1) ◽  
Author(s):  
Michal Koleška ◽  
Michal Šunka ◽  
Jaroslav Ernest
Keyword(s):  
Experimental Data ◽  
Fission Product ◽  
Research Reactor ◽  
Fuel Burnup ◽  
Spent Fuel ◽  
Axial Distribution ◽  
Operational Code ◽  
Spectrometric System ◽  
Type Fuel

A spectrometric system was developed for spent fuel burnup evaluations at the LVR-15 research reactor, which employed highly enriched (36%) IRT-2M-type fuel. Such a system allows the measurement of fission product axial distribution by measuring certain nuclides, such as Cs137, Cs134, and their ratios, respectively. Within the paper, a comparison between experimental data provided by the spectrometric system and calculations in operational code called NODER is provided.

Determination of fuel burnup distribution of a research reactor based on measurements at subcritical conditions

2018 ◽  
Vol 29 (12) ◽  
Author(s):  
Quang Binh Do ◽  
Hoai-Nam Tran ◽  
Quang Huy Ngo ◽  
Giang T. T. Phan
Keyword(s):  
Research Reactor ◽  
Fuel Burnup

scholarly journals Calculation of fuel burnup and radionuclide inventory for the HEU and potential LEU fuels in the IRT research reactor

2018 ◽  
Vol 11 ◽  
pp. 564-569 ◽  
Author(s):  
Saadou Aldawahrah ◽  
S. Dawahra ◽  
K. Khattab ◽  
G. Saba ◽  
M. Boush
Keyword(s):  
Research Reactor ◽  
Fuel Burnup ◽  
Radionuclide Inventory

Calculation of fuel burnup and excess reactivity using TRIGLAV code for the BAEC TRIGA research reactor

2020 ◽  
Vol 14 (4) ◽  
pp. 291
Author(s):  
Md. Abdul Malek Soner ◽  
Md. Ashraf Ali ◽  
P.K. Das ◽  
Shafiul Hossain ◽  
Md. Mizanur Rahman ◽  
...  
Keyword(s):  
Research Reactor ◽  
Fuel Burnup

scholarly journals Estimation of Fuel Burnup Rate for Core Conversion for the Nigeria Research Reactor-1 (NIRR-1) Fueled With 19.75% Enriched UO2 USING VENTURE PC Code

2020 ◽  
pp. 42-49
Author(s):  
J. A. Rabba ◽  
M. Y. Onimisi ◽  
D. O. Samson
Keyword(s):  
Uranium Dioxide ◽  
Research Reactor ◽  
Fuel Burnup ◽  
Reactor Operation ◽  
The Core ◽  
Computer Codes ◽  
Enriched Uranium ◽  
Conversion Study ◽  
Good Agreement

A standardized burnup analysis using VENTURE-PC computer codes system has been performed for the core conversion study of Nigeria Research Reactor-1. The result obtained from this analysis showed that the mass of Uranium decreases with increase in the number of days of reactor operation while the quantity of Plutonium continues to build up linearly. The buildup of the fissile isotope in the Low Enriched Uranium (LEU) core is very much greater than in the Highly Enriched Uranium (HEU) core. The quantity of Uranium-235 consumed and the amount of Plutonium-239 produce in the core of the reactor were 13.95 g and 0.766745 g respectively for the period of 11 years of reactor operation which is in good agreement with other literatures. This results obtained showed that uranium dioxide (UO2) fuel is a potential material for future Low Enriched Uranium (LEU) core conversion of Nigeria Research Reactor.

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