Development and Validation of a New Domestic Software for Dose Assessment during Normal and Accident Conditions in Nuclear Power Plants (NPPS).
Health Phys
; 122(6): 651-662, 2022 06 01.
Article
em En
| MEDLINE
| ID: mdl-33002967
ABSTRACT
ABSTRACT In this research, a comprehensive code called KIANA is developed based on the Gaussian plume model to simulate and predict the radiological consequences received through all the possible, reasonable, probable, and standard exposure pathways for NPPs and chemical facilities. To validate the KIANA code, a case study is modeled for Bushehr Nuclear Power Plant Unit One (BNPP-1), and the KIANA code results are compared with the results of the Final Safety Analysis Report (FSAR-2017) data of BNPP-1. To assess the performance of the KIANA code, the total dose due to the airborne pathway in accident conditions including small break LOCA (SBLOCA), large break LOCA (LBLOCA), and equivalent exposure dose for the thyroid gland of a group of infants and children age 1 to 8 y at BNPP-1, are investigated. The KIANA code results show that the total effective doses do not exceed the regulatory limit of 5 mSv for external and internal exposures and the regulatory limit of 50 mSv for thyroid equivalent dose. The KIANA code results indicate good agreement with the results of FSAR-2017.
Texto completo:
1
Coleções:
01-internacional
Base de dados:
MEDLINE
Assunto principal:
Monitoramento de Radiação
/
Acidente Nuclear de Fukushima
Tipo de estudo:
Prognostic_studies
Limite:
Child
/
Child, preschool
/
Humans
/
Infant
Idioma:
En
Revista:
Health Phys
Ano de publicação:
2022
Tipo de documento:
Article
País de afiliação:
Irã