Published December 2020
| Version v1
Book
On feasibility of using nitride fuel in MTR research reactor core: Comparison with U3O8 (LEU)
Creators
- 1. Nuclear and Radiological Regulatory Authority, Cairo (Egypt)
Description
In this paper, Uranium Nitride (UN) is used as a fuel to MTR (10 IAEA) research reactor, the core is fuelled with UN and U3O8 dispersed in aluminium matrix with same amount fissile uranium LEU (low Enrichment Uranium). The UN achieves initial Keff of 1.11184 with a fuel cycle length 120 days which is comparable to LEU. Thermal hydraulic analysis is performed using RELAP5 system code. The results indicated that UN-Al fuel gives better thermal hydraulic performance than U3O8 –Al fuel. UN-Al has lower peak fuel and clad temperature, this advance will retard the occurrence of critical phenomena such as departure from nucleate boiling (DNBR) and flow instability. (author)
Additional details
Identifiers
Publishing Information
- Publisher
- IAEA
- Imprint Place
- Vienna (International Atomic Energy Agency (IAEA))
- ISBN
- 978-92-0-131820-6
- Imprint Title
- Research Reactors: Addressing Challenges and Opportunities to Ensure Effectiveness and Sustainability. Summary of an International Conference. Supplementary Files
- Imprint Pagination
- vp.
- Series
- Proceedings Series
- Journal Page Range
- 8 p.
- ISSN
- 0074-1884
Conference
- Title
- Addressing Challenges and Opportunities to Ensure Effectiveness and Sustainability
- Acronym
- International Conference on Research Reactors
- Dates
- 25-29 Nov 2019
- Place
- Buenos Aires (Argentina)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 52011177
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ALUMINIUM; INSTABILITY; MATERIALS TESTING; NUCLEAR FUELS; NUCLEATE BOILING; REACTOR CORES; RESEARCH REACTORS; SLIGHTLY ENRICHED URANIUM; THERMAL HYDRAULICS; URANIUM NITRIDES; URANIUM OXIDES U3O8
- Descriptors DEC
- ACTINIDE COMPOUNDS; ACTINIDES; BOILING; CHALCOGENIDES; ELEMENTS; ENERGY SOURCES; ENRICHED URANIUM; FLUID MECHANICS; FUELS; HYDRAULICS; ISOTOPE ENRICHED MATERIALS; MATERIALS; MECHANICS; METALS; NITRIDES; NITROGEN COMPOUNDS; OXIDES; OXYGEN COMPOUNDS; PHASE TRANSFORMATIONS; PNICTIDES; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; RESEARCH AND TEST REACTORS; TESTING; URANIUM; URANIUM COMPOUNDS; URANIUM OXIDES
Optional Information
- Notes
- 12 refs., 5 figs., 3 tabs.
- Secondary number(s)
- IAEA-CN--277/P.3.02