Published October 2004
| Version v1
Report
Modelling non-standard mixed oxide fuels with the mechanistic code MACROS: Neutronic and heterogeneity effects
Description
MACROS is a computer code for the neutronic, thermal and mechanical analysis of fuel rods in nuclear reactors, which is developed at SCK-CEN. In the paper the recent developments made to cope with non-standard fuels are summarized with emphasis on neutronic effects and its outcomes. First results are presented of verification calculations made for reference fuel rods from the international DOMO project where differences between UO2 and homogeneous and heterogeneous MOX fuels have been extensively studied. (author)
Additional details
Identifiers
Publishing Information
- ISBN
- 92-0-111404-4
- Imprint Title
- Advanced fuel pellet materials and designs for water cooled reactors. Proceedings of a technical committee meeting
- Imprint Pagination
- 329 p.
- Journal Page Range
- p. 235-255
- ISSN
- 1011-4289
- Report number
- IAEA-TECDOC--1416
Conference
- Title
- Technical committee meeting on advanced fuel pellet materials and designs for water cooled reactors
- Dates
- 20-24 Oct 2003
- Place
- Brussels (Belgium)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 36018006
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- FUEL RODS; M CODES; MECHANICAL PROPERTIES; MIXED OXIDE FUELS; NEUTRON FLUX; PHYSICAL RADIATION EFFECTS; THERMAL ANALYSIS; URANIUM DIOXIDE
- Descriptors DEC
- ACTINIDE COMPOUNDS; CHALCOGENIDES; COMPUTER CODES; ENERGY SOURCES; FUEL ELEMENTS; FUELS; MATERIALS; NUCLEAR FUELS; OXIDES; OXYGEN COMPOUNDS; RADIATION EFFECTS; RADIATION FLUX; REACTOR COMPONENTS; REACTOR MATERIALS; SOLID FUELS; URANIUM COMPOUNDS; URANIUM OXIDES
Optional Information
- Contract/Grant/Project number
- Project FIKS-CT-2001-00141
- Notes
- 10 refs, 14 figs, 2 tabs