[3A01-05] Radiation-dose Evaluation and Environmental Assessment

[3A03] Applied example MCNP5 on ambient dose evaluation from nuclear facility

＊naoki zaima¹, masaki naganuma¹, sakao ryouta¹ (1.japan atomic energy agency)

Keywords:skyshine, Monte-Carlo tranport calculation code, nuclear facility

It's important to evaluate the ambient dose from nuclear fuel facility. Hitherto the deterministic calculation codes such as QAD or G33 are previously used. However the probabilistic calculation code such as Monte-Carlo transport code MCNP5 are recently used commonly. Therefore transformed calculation methods will be reported.