Abstract
In this research, the analysis methodology for Kuosheng BWR/6 nuclear power plant (NPP) decommissioning is established by using NRCDose3 code. NRCDose3 code includes XOQDOQ, GASPAR II, and LADTAP II programs that can assess atmospheric dispersion factor, gaseous radioactive effluents and offsite doses, and liquid radioactive releases and offsite doses, respectively. Therefore, this analysis methodology of NRCDose3 assesses the offsite doses of the gaseous radioactive effluents and liquid radioactive releases for Kuosheng NPP decommissioning. According to the analysis results, the results of NRCDose3 are consistent with Kuosheng NPP data.
-
Author contributions: All the authors have accepted responsibility for the entire content of this submitted manuscript and approved submission.
-
Research funding: None declared.
-
Conflict of interest statement: The authors declare no conflicts of interest regarding this article.
References
International Commission on Radiological Protection. (1996). ICRP report no. 72, Age-dependent dose to members of the public from intake of radionuclides, part 5. Compilation of ingestion and inhalation dose coefficients, ICRP 72. Ann. ICRP 21, 1–3, https://doi.org/10.1016/s0146-6453(00)89192-7.Search in Google Scholar
Taiwan Power Company (2001). Final safety analysis report for Kuosheng nuclear power station units 1 & 2 (FSAR).Search in Google Scholar
Taiwan Power Company (2018). Kuosheng nuclear power plant decommissioning plan.Search in Google Scholar
U.S. NRC (1977a). RG 1.111, methods for estimating atmospheric transport and dispersion of gaseous effluents in routine releases from light-water-cooled reactors, Revision 1.Search in Google Scholar
U.S. NRC (1977b). RG 1.109, calculation of annual doses to man from routine releases of reactor effluents for the purpose of evaluating compliance with 10 CFR part 50, Appendix I, Revision 1.Search in Google Scholar
U.S. NRC (1977c). RG 1.113, estimating aquatic dispersion of effluents from accidental and routine reactor releases for the purpose of implementing, Appendix I, Revision 1.Search in Google Scholar
U.S. NRC (1982). XOQDOQ: computer program for the meteorological evaluation of routine effluent releases at nuclear power stations, NUREG/CR-2919.Search in Google Scholar
U.S. NRC (1986). LADTAP II, technical reference and user guide, NUREG/CR-4013.Search in Google Scholar
U.S. NRC (1987). GASPAR II, technical reference and user guide, NUREG/CR-4653.Search in Google Scholar
U.S. NRC (2019). NRCDose3 code: user guide and technical manual.Search in Google Scholar
© 2021 Walter de Gruyter GmbH, Berlin/Boston
Articles in the same Issue
- Frontmatter
- Single-phase flow heat transfer characteristics in helically coiled tube heat exchangers
- Design and optimization of an integrated gamma ray scanning system for the uranium sample
- Numerical simulation of the effect of rod bowing on critical heat flux
- Flow and heat transfer characteristics of a nanofluid as the coolant in a typical MTR core
- Mathematical modeling of point kinetic equations with temperature feedback for reactivity transient analysis in MTR
- An enhanced formalism for the inverse reactor kinetics problem
- The establishment of analysis methodology of NRCDose3 for Kuosheng nuclear power plant decommissioning
- Analysis of SMART reactor core with uranium mononitride for prolonged fuel cycle using OpenMC
- Conceptual design of an innovative I&XC fuel assembly for a SMR based on neutronic/thermal-hydraulic calculations at the BOC
- Optimized fractional-order PID controller based on nonlinear point kinetic model for VVER-1000 reactor
- High rate X-ray radiation shielding ability of cement-based composites incorporating strontium sulfate (SrSO4) minerals
- Vibration analysis for predictive maintenance and improved reliability of rotating machines in ETRR-2 research reactor
- Calendar of events
Articles in the same Issue
- Frontmatter
- Single-phase flow heat transfer characteristics in helically coiled tube heat exchangers
- Design and optimization of an integrated gamma ray scanning system for the uranium sample
- Numerical simulation of the effect of rod bowing on critical heat flux
- Flow and heat transfer characteristics of a nanofluid as the coolant in a typical MTR core
- Mathematical modeling of point kinetic equations with temperature feedback for reactivity transient analysis in MTR
- An enhanced formalism for the inverse reactor kinetics problem
- The establishment of analysis methodology of NRCDose3 for Kuosheng nuclear power plant decommissioning
- Analysis of SMART reactor core with uranium mononitride for prolonged fuel cycle using OpenMC
- Conceptual design of an innovative I&XC fuel assembly for a SMR based on neutronic/thermal-hydraulic calculations at the BOC
- Optimized fractional-order PID controller based on nonlinear point kinetic model for VVER-1000 reactor
- High rate X-ray radiation shielding ability of cement-based composites incorporating strontium sulfate (SrSO4) minerals
- Vibration analysis for predictive maintenance and improved reliability of rotating machines in ETRR-2 research reactor
- Calendar of events