Characterization measurements of fluental and graphite in FiR1 TRIGA research reactor decommissioning waste

Author:

Räty Antti,Lavonen Tiina,Leskinen Anumaija,Likonen Jari,Postolache Cristian,Fugaru Viorel,Bubueanu George,Lungu Cristian,Bucsa Adrian

Funder

VTT Centre of Nuclear Safety ICP-MS laboratory

Publisher

Elsevier BV

Subject

Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference36 articles.

1. Metamorphosis of a 35 Years Old TRIGA Reactor into a Modern BNCT Facility,;Auterinen,1998

2. Auterinen, Iiro; Salmenhaara, Seppo, Current utilization and long term strategy of the Finnish TRIGA research reactor FiR 1, Proceedings of the 4th World TRIGA Users Conference, Lyon (France); 7-10 Sep 2008, INIS-FR--08-1293, 2008b. http://www.iaea.org/inis/collection/NCLCollectionStore/_Public/40/007/40007431.pdf.

3. Design of an epithermal neutron beam for the TRIGA reactor in Otaniemi;Auterinen,1994

4. The 250 kW FiR 1 TRIGA research reactor - international role in boron neutron capture therapy (BNCT) and regional role in isotope production, education and training, research reactors: safe management and effective utilization;Auterinen,2008

5. Rate and speciation of volatile carbon-14 and tritium releases from irradiated graphite;Baston;Mineral. Mag.,2012

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