The effective multiplication factor (keff) and the flux distribution in the Kartini reactor which used Uranium Zirconium Hydride (UZrH) as fuel, pure water (H2O) as moderators and cooland has been analyzed using Monte Carlo simulation. The flux distribution analyzed by splitting core reactor become 5 rings (B, C, D, E and F). The effective multiplication factor (keff) and flux distribution calculated by MCNP 4C with burn-up variation 0%, 2,5%, 5%, 7,5%, 10%, 12,5%, 15%. The result shows that the critical condition obtained from burn-up rate 0% up to 5%. The highest value of flux distribution in the middle, at ring B and the value gets smaller towards to edge of reactor core
Analisis laju reaksi neutron dalam sel bahan bakar nuklir pada reaktor cepat sangat penting dilakuka...
Analisis neutronik Lead-bismuth Cooled Fast Reactor (LFR) berdasarkan variasi daya keluaran telah d...
ABTRAKS The determination of neutron multiplication factor and distribution of neutron in the reacto...
Research of optimation fuel dimension have been done for PWR type with UO2 fuel, light water (H2O) m...
Telah dilakukan analisis neutronik pada Gas Cooled Fast Reactor (GCFR) dengan variasi umur teras da...
Analisis neutronik Sodium-Cooled Fast Reactor (SFR) berdasarkan variasi daya keluaran telah dilakuka...
Telah dilakukan analisis neutronik pada Gas Cooled Fast Reactor (GCFR) dengan variasi umur teras dan...
Telah dilakukan analisis neutronik pada reaktor SFR dengan variasi bahan bakar MOX, UN-PuN, dan U-Zr...
Telah dilakukan analisis perhitungan neutronik pada gas cooled fast reactor (GCFR) menggunakan progr...
Analisis kekritisan Sodium-Cooled Fast Reactor (SFR) berdasarkan variasi daya keluaran telah dilaku...
Analisis neutronik Super Critical Water Reactor (SCWR) menggunakan simulasi komputasi program SRAC t...
Telah dilakukan analisis kekritisan Lead-Cooled Fast Reactor (LFR) menggunakan program SRAC. Reaktor...
[Title: Neutronic Analysis of the criticality level of the nuscale reactor core with fuel usin...
Shield optimization and the calculation of neutron flux the coming out of the thermalizing column o...
Analisis kekritisan Sodium-Cooled Fast Reactor (SFR) berdasarkan variasi bahan bakar telah dilakukan...
Analisis laju reaksi neutron dalam sel bahan bakar nuklir pada reaktor cepat sangat penting dilakuka...
Analisis neutronik Lead-bismuth Cooled Fast Reactor (LFR) berdasarkan variasi daya keluaran telah d...
ABTRAKS The determination of neutron multiplication factor and distribution of neutron in the reacto...
Research of optimation fuel dimension have been done for PWR type with UO2 fuel, light water (H2O) m...
Telah dilakukan analisis neutronik pada Gas Cooled Fast Reactor (GCFR) dengan variasi umur teras da...
Analisis neutronik Sodium-Cooled Fast Reactor (SFR) berdasarkan variasi daya keluaran telah dilakuka...
Telah dilakukan analisis neutronik pada Gas Cooled Fast Reactor (GCFR) dengan variasi umur teras dan...
Telah dilakukan analisis neutronik pada reaktor SFR dengan variasi bahan bakar MOX, UN-PuN, dan U-Zr...
Telah dilakukan analisis perhitungan neutronik pada gas cooled fast reactor (GCFR) menggunakan progr...
Analisis kekritisan Sodium-Cooled Fast Reactor (SFR) berdasarkan variasi daya keluaran telah dilaku...
Analisis neutronik Super Critical Water Reactor (SCWR) menggunakan simulasi komputasi program SRAC t...
Telah dilakukan analisis kekritisan Lead-Cooled Fast Reactor (LFR) menggunakan program SRAC. Reaktor...
[Title: Neutronic Analysis of the criticality level of the nuscale reactor core with fuel usin...
Shield optimization and the calculation of neutron flux the coming out of the thermalizing column o...
Analisis kekritisan Sodium-Cooled Fast Reactor (SFR) berdasarkan variasi bahan bakar telah dilakukan...
Analisis laju reaksi neutron dalam sel bahan bakar nuklir pada reaktor cepat sangat penting dilakuka...
Analisis neutronik Lead-bismuth Cooled Fast Reactor (LFR) berdasarkan variasi daya keluaran telah d...
ABTRAKS The determination of neutron multiplication factor and distribution of neutron in the reacto...