Analysis of the Neutronic Characteristics of GFR-2400 Fast Reactor Using MCNPX Transport Code
- 1. High Institute for Engineering and Technology, Cairo (Egypt)
- 2. Nuclear and Radiological Regulatory Authority, Cairo (Egypt)
- 3. Faculty of Science, Physics Department, Ain Shams University, Cairo (Egypt)
- 4. Higher Technological Institute 10th of Ramadan City, Cairo (Egypt)
Description
The 2400 MW Gas Cooled Fast Reactor (GFR2400) is a promising potential candidate for future sustainable and economic nuclear power systems. It is a highly innovative system with advanced geometrical design and fuel materials (Ceramic fuel pellets of mixed uranium‐plutonium carbide within fuel pins). The active fuel region of this reactor is divided radially into two core zones of different fissile plutonium enrichments namely, inner core fuel assemblies (IC), and outer core fuel assemblies (OC). Using MCNPX transport code, 3D heterogeneous model of GFR2400 core has been designed to study the neutronic characteristics of the GFR2400 concept and to simulate its operation during a fuel cycle of a duration 1443 effective full power days. The obtained results show good agreement with previous studies and confirm the capability of the GFR2400 concept to achieve sustainability
Additional details
Publishing Information
- Journal Title
- Arab Journal of Nuclear Sciences and Applications (Online)
- Journal Volume
- 51
- Journal Issue
- 1
- Journal Page Range
- p. 177-188
- ISSN
- 2090-4258
INIS
- Country of Publication
- Egypt
- Country of Input or Organization
- Egypt
- INIS RN
- 49086928
- Subject category
- S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- CERAMICS; FUEL ASSEMBLIES; FUEL PELLETS; GCFR REACTOR; PLUTONIUM; URANIUM
- Descriptors DEC
- ACTINIDES; BREEDER REACTORS; ELEMENTS; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; GAS COOLED REACTORS; GCFR TYPE REACTORS; HELIUM COOLED REACTORS; METALS; PELLETS; REACTORS; TRANSURANIUM ELEMENTS