Monte Carlo Simulation of the Massachusetts Institute of Technology Research Reactor
- 1 April 1994
- journal article
- research article
- Published by Taylor & Francis in Nuclear Technology
- Vol. 106 (1) , 1-14
- https://doi.org/10.13182/nt94-a34946
Abstract
The three-dimensional continuous-energy MCNP Monte Carlo code is used to develop a versatile and accurate reactor physics model of the Massachusetts Institute of Technology Research Reactor II (MITR-II). The validation of the model against existing experimental data is presented. Core multiplication factors as well as fast neutron in-core flux measurements were used in the validation process. The agreement between the MCNP predictions and the experimentally determined values is very good, which indicates that the Monte Carlo model is correctly simulating the MITR-II.Keywords
This publication has 2 references indexed in Scilit:
- MCNP: Neutron benchmark problemsPublished by Office of Scientific and Technical Information (OSTI) ,1991
- MCNP: Photon benchmark problemsPublished by Office of Scientific and Technical Information (OSTI) ,1991