IAEA's (International Atomic Energy Agency) publication SSG-26 defines a methodology for calculating A1/A2 values. These values were conceived as limits for the transport of radioactive goods, to limit the public's exposure to radiation in the event of an accident. The limits ensure people involved in an accident receive an effective dose of no more than 50 mSv and a skin equivalent dose no greater than 500 mSv. The current values are based on five exposure scenarios taken from the Q-System, described in 1996. In 2013, the IAEA commissioned an international working group to improve the Q-System and calculate new limits for the transport of radioactive material. Within this working group, CERN has developed a set of models and an associated mathematical framework, and compiled them in a single piece of software. The primary purpose of the software is to compute and compare values produced by the different models under discussion. Later, the software could be distributed in a lighter version which will include the agreed upon regulatory model to determine the A1/A2 values.
The benchmark analysis of reactivity experiments in the TRIGA-II core at the Musashi Institute of Technology Research Reactor (Musashi reactor, 100 kW) was performed by a three-dimensional continuous-energy Monte Carlo code MCNP4A. The reactivity worth and integral reactivity curves of the control rods as well as the reactivity worth distributions of fuel and graphite elements were used in the validation process of the physical model and neutron cross section data from the ENDF /B-V evaluation. The calculated values of integral reactivity curves of the control rods were in agreement with the experimental data obtained by the period method. The integral worth measured by the rod drop method was also consistent with the calculation. The calculated values of the fuel and the graphite element worth distributions were consistent with the measured ones within the statistical error estimates. These results showed that the exact core configuration including the control rod positions to reproduce the fission source distribution in the experiment must be introduced into the calculation core for obtaining the precise solution. It can be concluded that our simulation model of the TRIGA-II core is precise enough to reproduce the control rod worth, fuel and graphite elements reactivity worth distributions.
scite is a Brooklyn-based organization that helps researchers better discover and understand research articles through Smart Citations–citations that display the context of the citation and describe whether the article provides supporting or contrasting evidence. scite is used by students and researchers from around the world and is funded in part by the National Science Foundation and the National Institute on Drug Abuse of the National Institutes of Health.
hi@scite.ai
10624 S. Eastern Ave., Ste. A-614
Henderson, NV 89052, USA
Copyright © 2024 scite LLC. All rights reserved.
Made with 💙 for researchers
Part of the Research Solutions Family.