Using SNAP and RADTRAD to Establish the Analysis Model for Maanshan PWR Plant

Authors: J. R. Wang, H. C. Chen, C. Shih, S. W. Chen, J. H. Yang, Y. Chiang

Abstract:

In this study, we focus on the establishment of the analysis model for Maanshan PWR nuclear power plant (NPP) by using RADTRAD and SNAP codes with the FSAR, manuals, and other data. In order to evaluate the cumulative dose at the Exclusion Area Boundary (EAB) and Low Population Zone (LPZ) outer boundary, Maanshan NPP RADTRAD/SNAP model was used to perform the analysis of the DBA LOCA case. The analysis results of RADTRAD were similar to FSAR data. These analysis results were lower than the failure criteria of 10 CFR 100.11 (a total radiation dose to the whole body, 250 mSv; a total radiation dose to the thyroid from iodine exposure, 3000 mSv).

Keywords: RADionuclide, transport, removal, and dose estimation, RADTRAD, symbolic nuclear analysis package, SNAP, dose, PWR.

Digital Object Identifier (DOI): doi.org/10.5281/zenodo.1131735

References:

[1] U. S. NRC, “RADTRAD: a simplified model for radionuclide transport and removal and dose estimation”, NUREG/CR-6604, 1997.
[2] Taiwan Power Company, “Maanshan Nuclear Power Station Final Safety Analysis Report (FSAR)”, 2013.
[3] W. C. Arcieri, D. L. Mlynarczyk, and L. Larsen, “SNAP/RADTRAD 4.0: description of models and methods”, NUREG/CR-7220, 2016.
[4] Bor-Jing Chang, “A simplified model for radionuclide transport and removal and dose estimation”, INER-7001, 2010.
[5] Yuan-Chien Wang, Jin-Sen Chung, “The radiological dose assessment of loss-of-coolant design basis accident in Maanshan final safety analysis report Using RADTRAD”, INER-10594, 2013.
[6] Cheng-Der Wang, “Control room dose analysis for Maanshan PWR plant during design basis loss of coolant accident”, INER-11555, 2014.
[7] U. S. NRC, 10 CFR 100.11, 1997.