Zobrazeno 1 - 10
of 11
pro vyhledávání: '"Jati Susilo"'
Autor:
Jati Susilo, Jsp Jupiter Sitorus Pane
Publikováno v:
Tri Dasa Mega, Vol 18, Iss 2, Pp 101-111 (2016)
FUEL BURN-UP DISTRIBUTION AND TRANSURANIC NUCLIDE CONTENTS PRODUCED AT THE FIRST CYCLE OPERATION OF AP1000. AP1000 reactor core was designed with nominal power of 1154 MWe (3415 MWth), operated within life time of 60 years and cycle length of 18 mont
Publikováno v:
Journal of Physics: Conference Series. 1198:022034
Reaktor Daya Eksperimental (RDE) is type of High Temperature Gas Cooled Reactor (HTGR) with nominal power 10 MWth that uses pebble bed type of sperical fuel. In the development of the RDE core design, as the earliest stage is to study characteristic
Autor:
Jati Susilo
Publikováno v:
KnE Energy. 1
AP1000 on the first cycle operation uses three types of UO2 fuel enrichments that are 2.35 w/o, 3.40 w/o and 4.50 w/o. To compensate excess reactivity, AP1000 uses an Integrated Fuel Burnable Absorber (IFBA) and a PYREX absorber as additional compens
Publikováno v:
Tri Dasa Mega, Vol 20, Iss 1, Pp 35-46 (2018)
For 30 years operation, some of the modifications to the RSG GAS core has been done, that are changes included the type of fuel from U3O8-Al to U3Si2-Al with the same density 2.96 gU/cc, the loading pattern of standard fuel elements/fuel control elem
Publikováno v:
Journal of Physics: Conference Series. 962:012030
The MCNP6 code contains numerous features, one of those is to determine the delayed neutron parameters. The accuracy of calculated delayed neutron parameters affect the accuracy of transient or dynamic condition. The objective of this paper is to det
Publikováno v:
Journal of Physics: Conference Series. 962:012031
bstract The using of a computer program for the PWR type core neutronic design parameters analysis has been carried out in some previous studies. These studies included a computer code validation on the neutronic parameters data values resulted from
Publikováno v:
Journal of Physics: Conference Series. 962:012059
Calculations of criticality of the AP1000 core due to the use of new edition of nuclear data library namely ENDF/B-VII and ENDF/B-VII.1 have been done. This work is aimed to know the accuracy of ENDF/B-VII.1 compared to ENDF/B-VII and ENDF/B-VI.8. in
Autor:
Jati Susilo, Endiah Pudjihastuti
Publikováno v:
Tri Dasa Mega, Vol 12, Iss 3 (2015)
Untuk meningkatkan kinerja teras RSG-GAS, maka telah dilakukan penelitian tentang penggunaan bahan bakar U3Si2-Al kerapatan 4,8 gU/cc. Penggunaan bahan bakar tersebut dapat meningkatkan panjang siklus operasi dari 20 menjadi 49 hari. Sehingga reaktor
Publikováno v:
Journal of Physics: Conference Series. 799:012023
The first short fuel pin containing natural UO2 pellet 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 res
Publikováno v:
Journal of Physics: Conference Series; 2018, Vol. 962 Issue 1, p1-1, 1p