Open AccessANALYSIS OF FUEL TEMPERATURE REACTIVITY COEFFICIENT OF THE PWR USING WIMS CODE
Author(s) -
Santo Paulus Rajagukguk,
Syaiful Bahkri,
Tukiran Surbakti
Publication year - 2022
Publication title -
jurnal teknologi reaktor nuklir tri dasa mega
Language(s) - English
Resource type - Journals
eISSN - 2527-9963
pISSN - 1411-240X
DOI - 10.17146/tdm.2022.24.1.6329
Subject(s) - nuclear engineering , nuclear data , control rod , light water reactor , pressurized water reactor , nuclear reactor , nuclear reactor core , research reactor , nuclear physics , environmental science , materials science , physics , engineering , neutron
The Fuel Temperature Reactivity Coefficient (FTRC) is an important parameter in design, control, and safety, particularly in PWR reactor. It is then very important to validate any new library for an accurate prediction of this parameter. The objective of this work is to determine the value of the FTRC parameter using the new WIMDS library based on ENDF/BVIII.0 nuclear data files. For this purpose, it is used a set of light water moderated lattice experiments as the PWR-1175 MWe experiment critical reactors, the reactor using UO2 fuel pellet. The analysis is used with WIMSD-5B lattice code with original cross-section libraries and WIMSD-5B with ENDF/B-VIII.0 new cross-section libraries. The results showed that the fuel temperatures reactivity coefficients for the PWR reactor using original libraries is – 3.10 pcm/K with enrichment of 3.1% but for ENDF/B-VlII.0 libraries is – 3.00 pcm/K. Compared to the experimental data of the reactor core, the difference is in the range of 6.9 % for ENDF/B-VIII.0 libraries. It can be concluded that for the reactor, it is better to use ENDF/B-VIII.0 libraries because the original library is not accurate anymore.