Mitigation of end flux peaking in CANDU fuel bundles using neutron absorbers
Description
End flux peaking (EFP) is a phenomenon where a build-up of neutrons occur at the end regions between two adjoining fuel bundles. EFP affects the axial flux profile of the reactor core, because peaks of high neutron flux occur in these regions. This can lead to an increase in the fission rate and therefore greater heat generation and higher temperatures in the fuel adjacent to the end regions. It is known that addition of neutron absorbers into fuel bundles will mitigate EFP, yet their implementation in Canada Deuterium Uranium (CANDU) type reactors using natural uranium fuel has not been pursued. To simulate the addition of a small amount of neutron absorbers strategically at the bundle ends, Monte Carlo N-Particle code (MCNP) 6 Beta 3.0 was used. Models of a single fuel bundle with two type of absorbers (Gd2O3/Eu2O3 mixture) placed in three locations were constructed. These locations include; placing the neutron absorbers within a thin disk at the bundle ends, in the CANLUB coating, and finally within the end pellets. This paper will present some preliminary results collected thus far. (author)
Additional details
Publishing Information
- Publisher
- Canadian Nuclear Society
- Imprint Place
- Toronto, Ontario (Canada)
- ISBN
- 978-1-926773-16-2
- Imprint Title
- PBNC 2014 : 19th Pacific Basin Nuclear Conference; 38th Annual Student Conference of the Canadian Nuclear Society and Canadian Nuclear Association
- Imprint Pagination
- 270 Megabytes
- Journal Page Range
- [5 p.]
Conference
- Title
- 19. Pacific Basin Nuclear Conference; 38. Annual Student Conference of the Canadian Nuclear Society and Canadian Nuclear Association
- Dates
- 24-28 Aug 2014
- Place
- Vancouver, British Columbia (Canada)
INIS
- Country of Publication
- Canada
- Country of Input or Organization
- Canada
- INIS RN
- 49016449
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- CANDU TYPE REACTORS; FUEL ELEMENT CLUSTERS; MONTE CARLO METHOD; NEUTRON ABSORBERS; NEUTRON FLUX; NEUTRON FLUX TILTING; REACTOR CORES; SIMULATION
- Descriptors DEC
- CALCULATION METHODS; FUEL ASSEMBLIES; HEAVY WATER MODERATED REACTORS; POWER REACTORS; PRESSURE TUBE REACTORS; RADIATION FLUX; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS
Optional Information
- Notes
- 3 refs., 2 figs.