Neutronic evaluation of a GFR of 100 MWt with reprocessed fuel and thorium using SCALE 6.0 and MCNPX
Creators
- 1. Departamento de Engenharia Nuclear – Escola de Engenharia. Universidade Federal de Minas Gerais, Av. Antônio Carlos, 6627, Pampulha, Belo Horizonte MG, CEP 31270-901 (Brazil)
- 2. Instituto Nacional de Ciências e Tecnologia de Reatores Nucleares Inovadores/CNPq (Brazil)
Description
A GFR core model with 100 MWt was evaluated using three different fuel compositions: conventional (U, Pu)C and two reprocessed fuels with transuranic (TRU) (Pu, Am, Np, Cm). One reprocessed by UREX+ technique and spiked with depleted uranium, (U,TRU)C, and the other reprocessed by the same technique but spiked with thorium, (Th,TRU)C. The reprocessed fuel came from a PWR standard fuel (33,000 MWd/T burned) with 3.1% of initial enrichment and left in the pool by 5 years. Some important nuclides were followed for burns and neutron absorption and kinf was evaluated 1400 days of burnup. Tests were also made for B4C absorber insertion and the temperature coefficient. The simulations were made comparing results of MCNPX and SCALE 6.0 programs. The goal is to validate the simulated model and evaluate the possibility to use TRU spiked with Th in a GFR conception. (author)
Files
49085778.pdf
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Additional details
Identifiers
Publishing Information
- Imprint Title
- International Conference on Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable Development (FR17). Programme and Papers
- Imprint Pagination
- vp.
- Journal Page Range
- 9 p.
- Report number
- IAEA-CN--245
Conference
- Title
- International Conference on Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable Development
- Acronym
- FR17
- Dates
- 26-29 Jun 2017
- Place
- Yekaterinburg (Russian Federation)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 49085778
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ABSORPTION; BURNS; BURNUP; COMPARATIVE EVALUATIONS; COMPUTERIZED SIMULATION; DEPLETED URANIUM; ENRICHMENT; FAST REACTORS; M CODES; NEUTRONS; NUCLEAR FUELS; PLUTONIUM; PWR TYPE REACTORS; REPROCESSING; S CODES; TEMPERATURE COEFFICIENT; THORIUM; THORIUM CYCLE; TRANSURANIUM COMPOUNDS
- Descriptors DEC
- ACTINIDES; BARYONS; COMPUTER CODES; DISEASES; ELEMENTARY PARTICLES; ELEMENTS; ENERGY SOURCES; ENRICHED URANIUM REACTORS; EPITHERMAL REACTORS; EVALUATION; FERMIONS; FUEL CYCLE; FUELS; HADRONS; INJURIES; MATERIALS; METALS; NUCLEONS; POWER REACTORS; REACTIVITY COEFFICIENTS; REACTOR MATERIALS; REACTORS; SEPARATION PROCESSES; SIMULATION; SORPTION; THERMAL REACTORS; TRANSURANIUM ELEMENTS; URANIUM; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 9 refs., 9 figs., 3 tabs.
- Secondary number(s)
- IAEA-CN--245-457