Uranium nitride fuels for application in Candu reactors
Creators
- 1. Kungliga Tekniska Hogskolan, Brinellvagen 8, 11428 Stockholm (Sweden)
- 2. Royal Military College, Kingston, Ontario K7K 7B4 (Canada)
Description
The physics of uranium nitride fuels used in Candu-6 reactors has been assessed by means of full core Monte-Carlo simulations. It is shown that the application of Unat15N allows for increasing the average residence time of a fuel bundle from 210 to 360 days, as compared to a conventional UnatO2 fuel. Whereas a 20% increase in coolant void worth is observed, the total power coefficient is reduced by half, due to a change in sign of the Doppler coefficient. Moreover, thanks to the better thermal conductivity of Un, the margin to fuel melt is raised considerably. Hence, uranium nitride could constitute a more efficient fuel for Candu reactors, while possibly allowing to extend the grace time for actuation of shut-down during a power transient. (Author)
Availability note (English)
Available from the Instituto Nacional de Investigaciones Nucleares, Centro de Informacion y Documentacion, 52750 Ocoyoacac, Estado de Mexico (MX), e-mail: mclaudia.gonzalez@inin.gob.mxAdditional details
Publishing Information
- Publisher
- Sociedad Nuclear Mexicana
- Imprint Place
- Ciudad de Mexico (Mexico)
- Imprint Pagination
- 9 p.
Conference
- Title
- reactor physics paving the way towards more efficient systems
- Acronym
- PHYSOR 2018
- Dates
- 22-26 Apr 2018
- Place
- Cancun, Q. R. (Mexico)
INIS
- Country of Publication
- Mexico
- Country of Input or Organization
- Mexico
- INIS RN
- 50013967
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- AUGMENTATION; CANDU TYPE REACTORS; COMPARATIVE EVALUATIONS; COMPUTERIZED SIMULATION; COOLANTS; DOPPLER COEFFICIENT; FUEL ELEMENT CLUSTERS; MONTE CARLO METHOD; NUCLEAR FUELS; POWER COEFFICIENT; PROFITS; RESIDENCE HALF-TIME; THERMAL CONDUCTIVITY; TRANSIENTS; URANIUM; URANIUM NITRIDES; VOIDS
- Descriptors DEC
- ACTINIDE COMPOUNDS; ACTINIDES; CALCULATION METHODS; ELEMENTS; ENERGY SOURCES; EVALUATION; FUEL ASSEMBLIES; FUELS; HEAVY WATER MODERATED REACTORS; MATERIALS; METALS; NITRIDES; NITROGEN COMPOUNDS; PHYSICAL PROPERTIES; PNICTIDES; POWER REACTORS; PRESSURE TUBE REACTORS; REACTIVITY COEFFICIENTS; REACTOR MATERIALS; REACTORS; SIMULATION; THERMAL REACTORS; THERMODYNAMIC PROPERTIES; URANIUM COMPOUNDS