FIR 1 Triga activity inventories for decommissioning planning

Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientificpeer-review


The objective of the study has been to estimate the residual activity in the decommissioning waste of TRIGA Mark II type research reactor FiR 1 in Finland. Neutron flux distributions were calculated with Monte Carlo code MCNP. These were used in ORIGEN-S point-depletion code to calculate the neutron induced activity of materials at different time points by modelling the irradiation history and radioactive decay. The knowledge of radioactive inventory of irradiated materials is important in the planning of the decommissioning activities and is essential for predicting the radiological impact to personnel and environment. Decommissioning waste consists mainly of ordinary concrete, aluminium, steel and graphite parts. Results include uncertainties due to assumptions on material compositions and possible diffusion of gaseous nuclides. Comparison to activity inventory estimates of two other decommissioned research reactors is also presented.
Original languageEnglish
Title of host publicationInternational Symposium on Preparation for Decommissioning (PREDEC 2016)
Publication statusPublished - 18 Feb 2016
MoE publication typeA4 Article in a conference publication
EventInternational Symposium on Preparation for Decommissioning (PREDEC 2016) - Lyon, France
Duration: 16 Feb 201618 Feb 2016


ConferenceInternational Symposium on Preparation for Decommissioning (PREDEC 2016)
Abbreviated titlePREDEC 2016
Internet address


Dive into the research topics of 'FIR 1 Triga activity inventories for decommissioning planning'. Together they form a unique fingerprint.

Cite this