@book{88fed9cc64a74e26a65369374edede4c,

title = "Computer modelling of radioactive source terms at a tokamak reactor",

abstract = "The Monte Carlo code MCNP has been used to create a simple three-dimensional mathematical model representing 1/12 of a tokamak fusion reactor for studies of the exposure rate level from neutrons as well as gamma rays from the activatedmaterials, and for later estimates of the consequences to the environment, public, and operating personnel. The model is based on the recommendations from the NET/INTOR workshops.",

keywords = "Ris{\o}-M-2482, M codes, Mathematical models, Monte Carlo method, Neutron transport, Tokamak devices, Three-dimensional calculations",

author = "A. Meide",

year = "1984",

language = "English",

isbn = "87-550-1077-6",

series = "Ris{\o}-M",

number = "2482",

publisher = "Ris{\o} National Laboratory",

}