Effect of fuel void change on PCMSR (Passive Compact Molten Salt Reactor) equilibrium core composition
Creators
- 1. Program Studi Teknik Nuklir, Jurusan Teknik Fisika, Fakultas Teknik – UGM, Yogyakarta (Indonesia)
Description
Nuclear energy becomes the most interesting alternative to substitute the fossil energy resources for the next decades. For this purpose the utilization of the next generation of nuclear power reactors must be increased. The nuclear power reactor will be functioned for electricity generation as well as for heat sources to supply several thermal industrial process. As the increasing of the utilization, the safety aspect of the next generation of nuclear power plants must be increased. Passive Compact Molten Salt Reactor (PCMSR)is a nuclear reactor using molten salt fuel (UF4ThF4-LiF)and graphite moderator. The using of U and The fuel makes a possibility to design the reactor core that has breeding capability at a thermal neutron spectrum. By the breeding capability, the utilization of nuclear fuel resources can be increased by factor 20 or more compared to the recent nuclear power plant technology. The using of molten salt fuel makes a possibility to operate the reactor at high temperature at low pressure. The calculation using SRAC computer code at equilibrium fuel composition shows that PCMSR has negative fuel void coefficient at its core and blanket, but has small positive fuel void coefficient at its heat exchanger. The reactor has small negative secondary coolant void coefficient at its heat exchanger. (author)
Additional details
Additional titles
- Original title (Indonesian)
- Pengaruh perubahan void bahan bakar pada PCMSR (Passive Compact Molten Salt Reactor) komposisi teras setimbang
Publishing Information
- Journal Title
- Jurnal Teknologi Reaktor Nuklir
- Journal Volume
- 9
- Journal Issue
- 2
- Journal Page Range
- p. 75-85
- ISSN
- 1411-240X
INIS
- Country of Publication
- Indonesia
- Country of Input or Organization
- Indonesia
- INIS RN
- 48079888
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- COMPUTER CODES; GRAPHITE; MOLTEN SALT FUELS; MOLTEN SALT REACTORS; PROGRAMMING; SIMULATION; THORIUM; URANIUM; VOIDS
- Descriptors DEC
- ACTINIDES; CARBON; ELEMENTS; ENERGY SOURCES; FUELS; LIQUID FUELS; MATERIALS; METALS; MINERALS; NONMETALS; NUCLEAR FUELS; REACTOR MATERIALS; REACTORS
Optional Information
- Notes
- 6 refs., 1 tab., 6 figs.