Document Type

Conference Proceeding


Proposed waste package designs will require the addition of neutron absorbing material to prevent the possibility of a sustained chain reaction occurring in the fuel in the event of water intrusion. Due to the low corrosion rates of the fuel matrix and the Zircaloy cladding, there is a possibility that the neutron absorbing material will corrode and leak from the waste container long before the subsequent release of fuel matrix material. An analysis of the release of fuel matrix and neutron absorber material based on a probabilistic model was conducted and the results were used to prepare input to KENO-V, an neutron criticality code. The results demonstrate that, in the presence of water, the computed values of k{sub eff} exceeded the maximum of 0.95 for an extended period of time.


Absorber; Absorbing; Alloys; Aluminum; Boron; Canister; Corrosion; Criticality (Nuclear engineering); Metal cladding; Neutron; Neutron absorbers; Nuclear; Oxidation; Package period; Poison; Radioactive waste canisters; Radioactive waste canisters – Corrosion; Release; Removal; Repository; Uranium; Value; Values Waste water; Zirconium alloys


Materials Science and Engineering | Mechanical Engineering | Nuclear Engineering


Conference: International high-level radioactive waste management conference,Las Vegas, NV (United States),22-26 May 1994


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