Zobrazeno 1 - 10
of 55
pro vyhledávání: '"I. Husnayani"'
Publikováno v:
Nuclear Technology. 206:1945-1950
The use of the RSG-GAS research reactor as a transmutation reactor is analyzed to study its effectiveness for transmuting long-lived fission products (LLFPs), particularly 129I and 99Tc. Both radio...
Autor:
SK Sri Kuntjoro, TS Tukiran Surbakti, Pande Made Udiyani, I. Husnayani, Muhammad Budi Setiawan
Publikováno v:
Web of Science
The evaluation of RSG-GAS research reactor for transmutation reactor was proposed to study its effectiveness to transmute minor actinides (MA), specifically Am-241, to support geologic storage/disposal. The Am-241 radionuclide was assumed to be disch
Publikováno v:
Urania, Vol 25, Iss 2 (2019)
CHARACTERISTICS OF RADIONUCLIDES ON THORIUM-CYCLE EXPERIMENTAL POWER REACTOR SPENT FUEL. There are several options of nuclear fuel utilisation in the HTGR-based Experimental Power Reactor (Reaktor Daya Eksperimental/RDE). Although mainly RDE utilises
Autor:
I. Husnayani, Muhammad Aziz Majidi
Publikováno v:
Journal of Physics: Conference Series. 1816:012073
Graphite is one kind of materials commonly used in nuclear reactor as neutron moderator and structural material. During the nuclear reactor operation, graphite is bombarded with high dose of radiation, especially neutron. This condition can cause dam
Publikováno v:
Journal of Physics: Conference Series. 1772:012047
High Temperature Gas-cooled Reactor (HTGR) is one of the Generation-IV reactors that has many advantages and very promising to be utilized in the future. National Nuclear Energy Agency of Indonesia (BATAN) has a program to build a non-commercial powe
Publikováno v:
Journal of Physics: Conference Series. 1198:022062
A first high quality coating TRISO high temperature gas-cooled reactor (HTGR) fuel has been developed since almost six decades ago. After Germany had invented the highly qualified HTR fuel in 2008, China contributed on the fabrication process of tri-
Publikováno v:
Journal of Physics: Conference Series. 1198:022037
BATAN priority activity supported by the Center for Nuclear Reactor Technology and Safety is the conceptual design documents and evaluation of experimental power reactor (RDE). Based on the design established, the radiation safety involving the dispe
Publikováno v:
AIP Conference Proceedings.
FLEXBLUE reactor is France’s small modular power reactor type of pressurized water reactor with 160 MWe. This reactor is based on ocean site which is suitable to be built in archipelagoes like Indonesia. The purpose of the present work is to evalua
Publikováno v:
AIP Conference Proceedings.
Reaktor Serba Guna GA Siwabessy (RSG-GAS) is a multipurpose Material Testing Reactor (MTR) with nominal power of 30 MW and currently utilized for material irradiation and other research purposes. When a sample material is put in the core of RSG-GAS,
Autor:
Ainon Hamzah, I. Husnayani, Pande Made Udiyani, M. Budi Setiawan, SK Sri Kuntjoro, Hery Adrial
Publikováno v:
AIP Conference Proceedings.
Experimental Power Reactor (RDE) is a power reactor with High Temperature Gas cooled Reactor (HTGR). The safety justification of the RDE design is that radiation safety can be guaranteed which guarantees the safety of radiation workers and the commun