Summary of - Validation of MCkeff code using ICSBEP results
Document Type
Article
Abstract
Indigenizing the development of scientific computing tools is essential as it brings knowledge on developing such tools. Also, Researchers need not rely on depreciated versions and the nuclear safety software, which is not available for us to use. The development of MCkeff is an indigenous attempt to estimate a nuclear safety parameter called criticality constant.
Research Goals and Hypothesis: To develop a computer program to solve the nuclear safety parameter (keff) of any user-required geometry and material configuration.
Methodological Approach: MCkeff transports millions of neutrons in user-defined geometry and fissionable material configuration to estimate the criticality constant using Monte Carlo methods. Before deploying any scientific tool, validating such codes against standard experimental results is paramount, and this work uses standard criticality benchmark problems. Results and Discoveries: The work here validates the code against the standard plutonium benchmark problems. The code MCkeff results align with the standard benchmark problems and can be deployed to study the actual new experiments.
Citation to the base paper: Sachin Shet, K.V. Subbaiah, P.M. Prajapati, Kapil Deo Singh, S. Anand, S.V. Suryanarayna, Validation of MCkeff code using ICSBEP results, Nuclear and Particle Physics Proceedings, 336–338, 2023, 26-28.
Publication Date
2023
Recommended Citation
Shet, Sachin; Subbaiah, K.V.; Prajapati, P.M.; Deo Singh, Kapil; Anand, S.; and Suryanarayna, S.V., "Summary of - Validation of MCkeff code using ICSBEP results" (2023). Open Access archive. 9253.
https://impressions.manipal.edu/open-access-archive/9253
