dc.contributor.author | Feng, Bo | |
dc.contributor.author | Kazimi, Mujid S. | |
dc.contributor.author | Forget, Benoit | |
dc.contributor.other | Massachusetts Institute of Technology. Nuclear Fuel Cycle Program | en_US |
dc.date.accessioned | 2013-03-11T15:52:41Z | |
dc.date.available | 2013-03-11T15:52:41Z | |
dc.date.issued | 2011-06-01 | |
dc.identifier.uri | http://hdl.handle.net/1721.1/77615 | |
dc.description.abstract | This study assesses the neutronic, thermal-hydraulic, and fuel performance aspects of using
nitride fuel in place of oxides in Pu-based high conversion light water reactor designs. Using
the higher density nitride fuel hardens the neutron energy spectrum and results in higher
breeding ratios.
The state-of-the-art high conversion light water reactor, the Resource-renewable
Boiling Water Reactor (RBWR), served as the template core upon which comparative studies
between nitride and oxide fuels were performed. A 1/3 core reactor physics model was
developed for the RBWR using the stochastic transport code MCNP. The code was coupled
with a lumped channel thermal-hydraulics 5-channel model for steady-state analyses. The
depletion code MCODE, which links MCNP with ORIGEN, was used for all burnup
calculations. Select physics parameters were calculated and with the exception of the void
coefficients, agreed with reported data. The void coefficients of the coupled core were
calculated to be slightly positive using two different methods (10% power increase and 5%
flow reduction).
The standard RBWR assembly designs, which use tight lattice hexagonal fuel rod
arrays, with oxide fuel were then replaced with various nitride fuel assembly designs to
determine the potential increase in breeding ratio, the potential to breed with pressurized water,
and the potential to improve the critical power ratio with a wider pin pitch. Without changing
the assembly geometry or discharge burnup, using nitride fuel resulted in a breeding ratio of
1.14. Using single-phase liquid water, the nitride fuel RBWR assembly resulted in a conversion
ratio of 1.00. Another nitride fuel assembly design with boiling water maintained a 1.04
breeding ratio while increasing the pitch-to-diameter ratio from 1.13 to 1.20. This modification
increased the hot assembly critical power ratio from 1.22 to 1.36, as calculated using the Liu-
2007 correlation.
A high-porosity nitride fuel is recommended for high burnup conditions, to
accommodate the nitride fuel’s higher swelling and less favorable mechanical properties
compared to the oxide fuel. The high porosity allows additional volume for pressure-induced
densification, alleviating swelling and subsequent cladding strain. To predict the performance
of high-porosity nitride fuel, fission gas and fuel behavior mechanistic models were developed
for high burnup and low-temperature conditions. These models were validated with reported
irradiation data and implemented, along with fuel material properties, into the steady-state fuel
behavior code FRAPCON-EP. Under simulated RBWR conditions, a fuel density no more than
85% of theoretical density is recommended to maintain satisfactory fuel performance. | en_US |
dc.description.sponsorship | Areva | en_US |
dc.description.sponsorship | Massachusetts Institute of Technology Study on the Future on The Nuclear Fuel Cycle | en_US |
dc.publisher | Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Nuclear Fuel Cycle Program | en_US |
dc.relation.ispartofseries | MIT-NFC;TR-124 | |
dc.title | Feasibility of Breeding in Hard Spectrum Boiling Water Reactors with Oxide and Nitride Fuels | en_US |
dc.type | Technical Report | en_US |
dc.contributor.mitauthor | Feng, Bo | |
dc.contributor.mitauthor | Kazimi, Mujid S. | |
dc.contributor.mitauthor | Forget, Benoit | |
dspace.orderedauthors | Feng, Bo; Kazimi, Mujid S.; Forget, Benoit | en_US |