Monte Carlo Simulations of the Water Draining Experiment of Giacint Critical Assembly
The MCNP6 computer program has been successfully extended to simulate reactor dynamics problems with moving parts of the geometries. Different from the dynamic method developed in other Monte Carlo codes, a movement scheme has been developed to account for the geometrical parts motion during the particle random walk. The MCNP6 computer program has been used to simulate two transient experiments of the Giacint critical assembly. The MCNP6 calculated total neutron flux was compared with that from the Serpent simulation. An excellent agreement was obtained between the results of the two Monte Caro computer programs. The MCNP6 calculated total neutron flux was also compared with the two measured transients. The MCNP6 results predicted a faster transient than the experimental data. The MCNP6 transient simulation was improved with an adjusted geometrical model which shifts the fuel rods slightly to match the measured reactivity worth due to the drained water. (c) 2021 Elsevier Ltd. All rights reserved.
- Research Organization:
- Argonne National Laboratory (ANL), Argonne, IL (United States)
- Sponsoring Organization:
- USDOE National Nuclear Security Administration (NNSA) - Office of Defense Nuclear Nonproliferation - Office of Material Management and Minimization (M3)
- DOE Contract Number:
- AC02-06CH11357
- OSTI ID:
- 1991354
- Journal Information:
- Annals of Nuclear Energy, Vol. 164
- Country of Publication:
- United States
- Language:
- English
Similar Records
SERPENT validation and optimization with mesh adaptive search on stereolithography geometry models
Calculating Control Rod Differential Worth Using Adjoint-Weighted Method