Advanced MCNP Simulation of the Neutron and Photon Flux and Absorbed Dose Rates for the SLOWPOKE-2 Nuclear Reactor at the Royal Military College of Canada. (1st December 2020)

• Record Type: Journal Article
• Authors: Rook, J. C.; Weber, K. P.; Corcoran, E. C.
• Is Part Of: Nuclear technology. Volume 206:Number 12(2020)
• Page Start: 1861
• Page End: 1874
• Publication Date: 2020-12-01
• Subjects: MCNP -- Royal Military College of Canada -- SLOWPOKE-2 -- absorbed dose -- neutron flux; Nuclear engineering -- Periodicals; Nuclear engineering; Nuclear Physics; Periodicals; Periodicals; 621.48
• DOI: 10.1080/00295450.2020.1720557
• Languages: English
• ISSNs: 1943-7471

Abstract

Abstract: For irradiation experiments (e.g., of per- and polyfluoroalkyl substances), values of nuclear particle flux and absorbed dose rates were obtained for the Safe LOW-POwer Kritical Experiment-2 (SLOWPOKE-2) nuclear reactor at the Royal Military College of Canada using extensive simulations of the reactor core via the Monte Carlo N-Particle code, version 6 (MCNP6). Calculations from this work were compared to data from previously conducted experimental and simulation work to ensure simulation fidelity. In addition, reactor core burnup calculations were conducted using the fuel-depletion capability in MCNP6.1 to address the 30+ years of SLOWPOKE-2 reactor use. The combined absorbed dose rate in the inner irradiation sites was simulated to be 36 ± 1 kGy h −1 at a 10-kW(thermal) power setting, specifically, 20 ± 6 kGy h −1 from neutrons and 16 ± 5 kGy h −1 from photons.