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Calculation method of containment dose rate based on MELCOR and MCNP codes
Calculation method of containment dose rate based on MELCOR and MCNP codes
2015
Shi Xiaolei
Xu Qian
Wei Yansong
Ji Songtao
Keywords:
MELCOR
Containment
Nuclear engineering
Environmental science
dose rate
Thermal power station
Accident management
nuclear facilities
calculation methods
Correction
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