Detailed source term estimation and atmospheric dispersion analysis for the Fukushima Dai-ichi Nuclear Power Plant accident

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Monday, 3 February 2014: 11:15 AM
Room C206 (The Georgia World Congress Center )
Genki Katata, Japan Atomic Energy Agency, Ibaraki, Japan; and M. Chino, M. Ota, H. Nagai, H. Terada, and M. Kajino

Temporal variations of release amounts of radionuclides during the Fukushima Dai-ichi Nuclear Power Plant (FNPP1) accident and their dispersion process are essential to evaluate the environmental impacts and resultant radiological doses to the public. Here, we estimated a detailed time trend of atmospheric releases during the accident by coupling additionally obtained monitoring data of air dose rate near the plant, parameters for the reactor events, and atmospheric dispersion simulation by WSPEEDI-II (Worldwide version of System for Prediction of Environmental Emergency Dose Information). New schemes for wet, dry, and fog depositions of radioactive gas and particle were incorporated. The reverse estimation method based on the simulation by the modified WSPEEDI-II assuming unit release rate (1 Bq h-1) was adopted to estimate the source term at the FNPP1. The modified WSPEEDI-II using the newly estimated source term well reproduced local and regional patterns of air dose rate and surface deposition of I-131 and Cs-137 obtained by airborne observations. The results suggested that the major release of radionuclides from the FNPP1 occurred in the following periods during March 2011: afternoon on the 12th when the venting and hydrogen explosion occurred at Unit 1, midnight on the 14th when several openings of SRV (steam relief valve) were conducted at Unit 2, morning and night on the 15th, and morning on the 16th. Our dispersion simulations also revealed that the highest radioactive contamination areas around FNPP1 were created from 15th to 16th March by complicated interactions among rainfall (wet deposition), plume movements, and phase properties (gas or particle) of I-131 and release rates associated with reactor pressure variations in Units 2 and 3.