FiR1 TRIGA research reactor decommissioning project

Research output: Chapter in Book/Report/Conference proceedingConference abstract in proceedingsScientific

Abstract

FiR1 is a 250 kW TRIGA Mark II type open pool reactor from General Atomics. It has been in operation for education, research, BNCT treatments and isotope production in Finland for years 1962-2015 and is planned to be decommissioned in following few years. Overall the reactor has been in use for around 11500 MWh. Radioactive waste will consist mainly of concrete, steel, aluminium, graphite and BNC Fluental neutron moderator materials. At first, the presentation introduces FiR1 reactor history and scientific use of it. This is followed by an indicative schedule of the VTT decommissioning project and on-going work. This includes licensing, agreements and procurement processes on dismantling planning, dismantling waste management and return of SNF. We present the calculation system for the activity inventories in the reactor structures and preliminary activity measurements in different materials. Some planned dismantling methods are illustrated and an outlook to future steps is presented.
Original languageEnglish
Title of host publicationProceedings of the Workshop on Current and Emerging methods for Optimising Safety and Efficiency in Nuclear Decommissioning
PublisherOECD
Number of pages1
Publication statusPublished - 2017
EventWorkshop on Current and Emerging methods for Optimising Safety and Efficiency in Nuclear Decommissioning - Sarpborg, Norway
Duration: 7 Feb 20179 Feb 2017

Workshop

WorkshopWorkshop on Current and Emerging methods for Optimising Safety and Efficiency in Nuclear Decommissioning
CountryNorway
CitySarpborg
Period7/02/179/02/17

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decommissioning
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radioactive waste
waste management
aluminum
steel
education
isotope
reactor
project
history
material

Cite this

Räty, A., Airila, M., Kotiluoto, P., Vilkamo, O., Kekki, T., Auterinen, I., ... Juutilainen, P. (2017). FiR1 TRIGA research reactor decommissioning project. In Proceedings of the Workshop on Current and Emerging methods for Optimising Safety and Efficiency in Nuclear Decommissioning OECD.
Räty, Antti ; Airila, Markus ; Kotiluoto, Petri ; Vilkamo, Olli ; Kekki, Tommi ; Auterinen, Iiro ; Calonius, Kim ; Juutilainen, Pauli. / FiR1 TRIGA research reactor decommissioning project. Proceedings of the Workshop on Current and Emerging methods for Optimising Safety and Efficiency in Nuclear Decommissioning. OECD, 2017.
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abstract = "FiR1 is a 250 kW TRIGA Mark II type open pool reactor from General Atomics. It has been in operation for education, research, BNCT treatments and isotope production in Finland for years 1962-2015 and is planned to be decommissioned in following few years. Overall the reactor has been in use for around 11500 MWh. Radioactive waste will consist mainly of concrete, steel, aluminium, graphite and BNC Fluental neutron moderator materials. At first, the presentation introduces FiR1 reactor history and scientific use of it. This is followed by an indicative schedule of the VTT decommissioning project and on-going work. This includes licensing, agreements and procurement processes on dismantling planning, dismantling waste management and return of SNF. We present the calculation system for the activity inventories in the reactor structures and preliminary activity measurements in different materials. Some planned dismantling methods are illustrated and an outlook to future steps is presented.",
author = "Antti R{\"a}ty and Markus Airila and Petri Kotiluoto and Olli Vilkamo and Tommi Kekki and Iiro Auterinen and Kim Calonius and Pauli Juutilainen",
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Räty, A, Airila, M, Kotiluoto, P, Vilkamo, O, Kekki, T, Auterinen, I, Calonius, K & Juutilainen, P 2017, FiR1 TRIGA research reactor decommissioning project. in Proceedings of the Workshop on Current and Emerging methods for Optimising Safety and Efficiency in Nuclear Decommissioning. OECD, Workshop on Current and Emerging methods for Optimising Safety and Efficiency in Nuclear Decommissioning, Sarpborg, Norway, 7/02/17.

FiR1 TRIGA research reactor decommissioning project. / Räty, Antti; Airila, Markus; Kotiluoto, Petri; Vilkamo, Olli; Kekki, Tommi; Auterinen, Iiro; Calonius, Kim; Juutilainen, Pauli.

Proceedings of the Workshop on Current and Emerging methods for Optimising Safety and Efficiency in Nuclear Decommissioning. OECD, 2017.

Research output: Chapter in Book/Report/Conference proceedingConference abstract in proceedingsScientific

TY - CHAP

T1 - FiR1 TRIGA research reactor decommissioning project

AU - Räty, Antti

AU - Airila, Markus

AU - Kotiluoto, Petri

AU - Vilkamo, Olli

AU - Kekki, Tommi

AU - Auterinen, Iiro

AU - Calonius, Kim

AU - Juutilainen, Pauli

N1 - abstract, presentation NEA-RWMC-WPDD--2017-02

PY - 2017

Y1 - 2017

N2 - FiR1 is a 250 kW TRIGA Mark II type open pool reactor from General Atomics. It has been in operation for education, research, BNCT treatments and isotope production in Finland for years 1962-2015 and is planned to be decommissioned in following few years. Overall the reactor has been in use for around 11500 MWh. Radioactive waste will consist mainly of concrete, steel, aluminium, graphite and BNC Fluental neutron moderator materials. At first, the presentation introduces FiR1 reactor history and scientific use of it. This is followed by an indicative schedule of the VTT decommissioning project and on-going work. This includes licensing, agreements and procurement processes on dismantling planning, dismantling waste management and return of SNF. We present the calculation system for the activity inventories in the reactor structures and preliminary activity measurements in different materials. Some planned dismantling methods are illustrated and an outlook to future steps is presented.

AB - FiR1 is a 250 kW TRIGA Mark II type open pool reactor from General Atomics. It has been in operation for education, research, BNCT treatments and isotope production in Finland for years 1962-2015 and is planned to be decommissioned in following few years. Overall the reactor has been in use for around 11500 MWh. Radioactive waste will consist mainly of concrete, steel, aluminium, graphite and BNC Fluental neutron moderator materials. At first, the presentation introduces FiR1 reactor history and scientific use of it. This is followed by an indicative schedule of the VTT decommissioning project and on-going work. This includes licensing, agreements and procurement processes on dismantling planning, dismantling waste management and return of SNF. We present the calculation system for the activity inventories in the reactor structures and preliminary activity measurements in different materials. Some planned dismantling methods are illustrated and an outlook to future steps is presented.

M3 - Conference abstract in proceedings

BT - Proceedings of the Workshop on Current and Emerging methods for Optimising Safety and Efficiency in Nuclear Decommissioning

PB - OECD

ER -

Räty A, Airila M, Kotiluoto P, Vilkamo O, Kekki T, Auterinen I et al. FiR1 TRIGA research reactor decommissioning project. In Proceedings of the Workshop on Current and Emerging methods for Optimising Safety and Efficiency in Nuclear Decommissioning. OECD. 2017