Methodology for analyzing dose consequence using atmospheric dispersion code A2CDOSE
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Yu Chiang
,
Chung-hsin Lu
Abstract
The experience of Fukushima brings out the importance of the emergency response plan during or after a severe nuclear power plant (NPP) accident. To deal with the accident emergency response situation, the National Atomic Research Institute (NARI) in Taiwan developed an emergent radiological dose evaluation system with the Central Weather Administration (CWA) called “A2CDOSE”. A2CDOSE can evaluate the eight-day projected dose after a nuclear accident and provide the predicted dose consequences for decision-making. Nevertheless, a source term generation method was still needed during the accident. This study chose MELCOR as the comparison target for the source term simulation issue with RASCAL. A MELCOR calculation of Maanshan NPP was built and a 5 % containment leakage was set for both MELCOR and RASCAL source term calculations. It seems the calculations of noble gases were consistent between MELCOR and RASCAL. However, the Cs-137 and I-131 calculated by MELCOR were twice compared to the RASCAL results, which may have a chance to cause different calculations of public protective actions during an accident. After the source term analysis, several atmospheric dispersion cases were simulated by A2CDOSE and RASCAL for further comparison.
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Research ethics: Not applicable.
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Author contributions: The authors have accepted responsibility for the entire content of this manuscript and approved its submission.
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Competing interests: The authors states no conflict of interest.
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Research funding: None declared.
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Data availability: Not applicable.
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Articles in the same Issue
- Frontmatter
- Multilateral evaluation of the effects of utilizing thorium oxide in the Bushehr VVER-1000 reactor
- Comparison of modeling methods for the effective diffusivities of IO3− estimated in compacted bentonite using through-diffusion tests under aerobic conditions
- Analysis of initial core and time dependent fuel burnup for high temperature testing reactors (HTTRs)
- A detection and defense security system design for nuclear waste storage against stealth terrorists attack
- Optimization of ECR assisted pre-ionization in GLAST-III via Multiphysics simulation
- Fuzzy reliability algorithm for the shutdown system of research reactor
- System theory safety analysis of network malfunction in nuclear power plant distributed control systems
- Two phase flow analysis of micro channel evaporator to investigate effect of geometry on pressure and heat transfer coefficient with respect to volume of fraction
- Methodology for analyzing dose consequence using atmospheric dispersion code A2CDOSE
- Reliability analysis of digital reactor protection systems in floating nuclear power plants
- Study on comprehensive evaluation method of mental workload level
- Integrating reliability analysis into MBSE for FPGA-based safety critical I&C system design in nuclear power plants
- Calendar of events
