The Aqueous Homogeneous Reactor (AHR) is a non-power nuclear reactor for producing medical isotope. AHR is operated at power level of 2 MW and fueled with UO2SO4·3H2O. The fraction of fuel and water consist of 95% water and 5% UO2SO4. The enrichment of reactor fuel is 20%. AHR is operated at the temperature of 80°C. The geometry of AHR is cylindrical which has diameter of 100 cm and 100 cm height. The reactor core has a dimension of 60 cm diameter and 60 cm in height. The fuel cell geometry of AHR is hexagonal, the tube is placed inside the fuel cell that contains water as moderator and coolant. The tube is made of stainless steel-347 and UO2SO4·3H2O is placed outside the tube. Citation is used to calculate multiplication factor of the r...
The solution-type research reactors placed in operation by Atomics International fall into three pow...
The thermohydraulic aspect utilization on a nuclear reactor is very dominant, because the system giv...
A study was performed comparing the performance of UO2 and (Th,U-233)O2 fuel in small long-life PWR....
Considerable interest has been expressed for developing a stable U.S. production capacity for medica...
Analysis of the amount of 99Mo production has been done by neutronic simulation using MCNPX software...
Aqueous Homogeneous Ractor (AHR) yang dikaji, termasuk jenis reaktor homogen karena bahan bakar dan ...
Radioisotope 99Mo is one of the most essential radioisotopes in nuclear medicine. Its production in ...
ABTRAKS The determination of neutron multiplication factor and distribution of neutron in the reacto...
This report describes the Sandia National Laboratories Medical Isotope Reactor and hot cell facility...
Telah dilakukan penelitian tentang Studi Parameter Reaktor Termal Pressurized Water Reactor (PWR) Be...
The Advanced High-Temperature Reactor (AHTR) is a design concept for a central station-type [1500 MW...
ABSTRACT Nuclear Reactor Technology is going continually improved. For the future, there is a term ...
ABSTRAK TEKNOLOGI KOPLING PEMBANGKIT DESALINASI NUKLIR. Pada prinsipnya kebutuhan energi sebuah inst...
KLT-40S nuclear reactor is a small modular floating nuclear power plant made by Russia as a conventi...
The research of desain of super critical water reactor (SCWR) thorium fuel has been done. The object...
The solution-type research reactors placed in operation by Atomics International fall into three pow...
The thermohydraulic aspect utilization on a nuclear reactor is very dominant, because the system giv...
A study was performed comparing the performance of UO2 and (Th,U-233)O2 fuel in small long-life PWR....
Considerable interest has been expressed for developing a stable U.S. production capacity for medica...
Analysis of the amount of 99Mo production has been done by neutronic simulation using MCNPX software...
Aqueous Homogeneous Ractor (AHR) yang dikaji, termasuk jenis reaktor homogen karena bahan bakar dan ...
Radioisotope 99Mo is one of the most essential radioisotopes in nuclear medicine. Its production in ...
ABTRAKS The determination of neutron multiplication factor and distribution of neutron in the reacto...
This report describes the Sandia National Laboratories Medical Isotope Reactor and hot cell facility...
Telah dilakukan penelitian tentang Studi Parameter Reaktor Termal Pressurized Water Reactor (PWR) Be...
The Advanced High-Temperature Reactor (AHTR) is a design concept for a central station-type [1500 MW...
ABSTRACT Nuclear Reactor Technology is going continually improved. For the future, there is a term ...
ABSTRAK TEKNOLOGI KOPLING PEMBANGKIT DESALINASI NUKLIR. Pada prinsipnya kebutuhan energi sebuah inst...
KLT-40S nuclear reactor is a small modular floating nuclear power plant made by Russia as a conventi...
The research of desain of super critical water reactor (SCWR) thorium fuel has been done. The object...
The solution-type research reactors placed in operation by Atomics International fall into three pow...
The thermohydraulic aspect utilization on a nuclear reactor is very dominant, because the system giv...
A study was performed comparing the performance of UO2 and (Th,U-233)O2 fuel in small long-life PWR....