We found a match
Your institution may have access to this item. Find your institution then sign in to continue.
- Title
Neutronic investigation of ALFRED lead-Cooled fast reactor core using monte carlo modeling.
- Authors
Ganjaroodi, Saeed Zare; Zarifi, Ehsan
- Abstract
A Lead-Cooled Fast Reactor (LFR) is one of the six advanced fourth-generation reactors that many countries have been interested in designing, constructing, or develop them in the world. ALFRED reactor design investigated in this paper has 125 (MW) electric power and is being cooled by lead. The main purpose of the ALFRED project is to design and construct a reactor with high safety performance and reliability in all operation modes. In the present study, Monte Carlo codes MCNPX and SuperMC are used to calculate the neutronic parameters of the ALFRED reactor core including effective multiplication factor, kinetic parameters, neutron flux, and power distribution based on the latest design data. According to the results, the insertion of the control rods into the core can move the maximum flux height of about 40% to 50% to the end. Also, comparing codes' results show an appropriate consistency.
- Subjects
NUCLEAR reactor cores; FAST reactors; RESEARCH reactors; CONTROL elements (Nuclear reactors); NEUTRON flux; DATABASE design; ELECTRIC power
- Publication
Atomic Energy, 2023, Vol 134, Issue 3/4, p264
- ISSN
1063-4258
- Publication type
Article
- DOI
10.1007/s10512-024-01054-2