Criticality Safety Calculation and Analysis for NPP Transportation of Fuel Assemblies

Dajie Zhuang

2023

Abstract

Nuclear criticality safety was calculated by MC code for transportation activity of fuel assemblies to Sanmen Nuclear Power Plant. Calculation result shows that the transportation of fuel assemblies meets the corresponding criticality safety requirements. In the calculation, eight criticality benchmark experiments for Low-Enriched Uranium rods lattice from NUREG/CR-6361 of the U.S. NRC was selected, and was validated calculation by SuperMC. Thereby, the result of criticality calculation for transportation of fuel assemblies with SuperMC code becomes more reliable.

Paper Citation

in Harvard Style

Zhuang D. (2023). Criticality Safety Calculation and Analysis for NPP Transportation of Fuel Assemblies. In Proceedings of the 1st International Conference on Data Processing, Control and Simulation - Volume 1: ICDPCS; ISBN 978-989-758-675-0, SciTePress, pages 51-57. DOI: 10.5220/0012145900003562

in Bibtex Style

@conference{icdpcs23,
author={Dajie Zhuang},
title={Criticality Safety Calculation and Analysis for NPP Transportation of Fuel Assemblies},
booktitle={Proceedings of the 1st International Conference on Data Processing, Control and Simulation - Volume 1: ICDPCS},
year={2023},
pages={51-57},
publisher={SciTePress},
organization={INSTICC},
doi={10.5220/0012145900003562},
isbn={978-989-758-675-0},
}

in EndNote Style

TY - CONF

JO - Proceedings of the 1st International Conference on Data Processing, Control and Simulation - Volume 1: ICDPCS
TI - Criticality Safety Calculation and Analysis for NPP Transportation of Fuel Assemblies
SN - 978-989-758-675-0
AU - Zhuang D.
PY - 2023
SP - 51
EP - 57
DO - 10.5220/0012145900003562
PB - SciTePress