title: Comparison of measured and calculated concrete and rebar specific activity during decommissioning of the Dalhousie SLOWPOKE-2 reactor.
abstract: Following the defuelling and dismantling of the Dalhousie University SLOWPOKE-2 Reactor (DUSR) in 2011, the reactor pool concrete and rebar were sampled to support the unconditional free release of the material such that the facility could be classified for unrestricted use. A detailed MCNP5 model of the critical core assembly was simulated to calculate the thermal, intermediate and fast neutron flux profile below the reactor pool floor. The neutron fluxes were used to calculate the specific activity of significant radionuclides in the concrete and rebar. The calculated specific activity and consequently the calculated neutron fluxes were validated at a number of sample locations. The calculated concrete and rebar specific activity were found to be in good agreement with the measured specific activity at the sample locations. The unrestricted use of the facility was granted through the approval of the licence to abandon the facility in August 2011.
authors: Candu Energy Incorporated, 2285 Speakman Drive, Mississauga, ON, Canada L5K1B2. philip.smith@candu.com
authors: Philip G
authors: PG
authors: Smith
authors: Dave
authors: D
authors: Everall
authors: Imelda
authors: I
authors: Ariani
authors: Kwok
authors: K
authors: Tsang
mesh_terms: D003252:Construction Materials / Q000032:analysis*; D003666:Decontamination / Q000295:instrumentation* / Q000379:methods*; D005160:Facility Design and Construction / Q000379:methods*; D009502:Neutrons; D009688:Nuclear Reactors; D011850:Radioactive Waste / Q000032:analysis*
chemical_list: D011850:Radioactive Waste