Space and Time Distribution of Pu Isotopes inside The First Experimental Fuel Pin Designed for PWR and Manufactured in Indonesia

International Conference on Advances in Nuclear Science and Engineering 2015

Suwardi^1,2 ; Setiawan, J.^1,2 ; Susilo, J.^2

Center for Nuclear Fuel Technology-BATAN, Puspiptek Bld.20, Tangerang-Selatan

15310, Indonesia^1

Center for Nuclear Safety Technology-BATAN, Puspiptek Bld.60, Tangerang-Selatan

15310, Indonesia^2

关键词: Model calculations;    Modified designs;    Numerical parameters;    Pellet diameters;    Performance analysis;    Performance aspects;    Post irradiation examinations;    Statistical experiments;   

Others  :  https://iopscience.iop.org/article/10.1088/1742-6596/799/1/012023/pdf
DOI  :  10.1088/1742-6596/799/1/012023

来源: IOP

【 摘 要 】

The first short fuel pin containing natural UO2pellet in Zry4 cladding has been prepared and planned to be tested in power ramp irradiation. An irradiation test should be designed to allow an experiment can be performed safely and giving maximum results of many performance aspects of design and manufacturing. Performance analysis to the fuel specimen shows that the specimen is not match to be used for power ramp testing. Enlargement by 0.20 mm of pellet diameter has been proposed. The present work is evaluation of modified design for important aspect of isotopic Pu distribution during irradiation test, because generated Pu isotopes in natural UO2 fuel, contribute more power relative to the contribution by enriched UO2 fuel. The axial profile of neutrons flux have been chosen from both experimental measurement and model calculation. The parameters of ramp power has been obtained from statistical experiment data. A simplified and typical base-load commercial PHWR profile of LHR history has been chosen, to determine the minimum irradiation time before ramp test can be performed. The data design and Mat pro XI materials properties models have been chosen. The axial profile of neutrons flux has been accommodated by 5 slices of discrete pin. The Pu distribution of slice-4 with highest power rate has been chosen to be evaluated. The radial discretion of pellet and cladding and numerical parameter have been used the default best practice of TU. The results shows that Pu 239 increased rapidly. The maximum burn up of slice 4 at upper the median slice, it reached nearly 90% of maximum value at about 6000 h with peak of 0.8%a Pu/HM at 22000 h, which is higher than initial U 235. Each 240, 241 and 240 Pu grows slower and ends up to 0.4, 0.2 and 0.18 % respectively. This results can be used for verification of other aspect of fuel behavior in the modeling results and also can be used as guide and comparison to the future post irradiation examination for Pu isotopes distribution.