Shielding design and calculations for the Finnish BNCT facility

Petri Kotiluoto, Pekka Hiismäki, Iiro Auterinen, Tiina Seppälä, Carita Aschan

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

Abstract

In the radiation shielding design of the Finnish Boron Neutron Capture Therapy (BNCT) facility,1 protecting the facility personnel from radiation exposure and to limit the whole body dose of the patient have been the primary safety concerns. Before the construction work of the irradiation room with heavy concrete walls and roof was started, the technical designs were verified by calculations. A shielding design limit of dose rate under 20µSv/h was set for laboratory area outside the irradiation room. For the shielding design purposes different materials and material thicknesses were tested by modelling of the materials and geometry and calculating the corresponding radiation levels. Shielding design calculations were made by two-dimensional radiation transport code DORT.
Original languageEnglish
Title of host publicationFrontiers in Neutron Capture Therapy
EditorsM. F. Hawthorne, K. Shelly, R. J. Wiersema
PublisherSpringer
Pages623-628
Volume1
ISBN (Electronic)978-1-4615-1285-1
ISBN (Print)978-1-4613-5478-9
DOIs
Publication statusPublished - 2001
MoE publication typeA4 Article in a conference publication
Event8th International Symposium on Neutron Capture Therapy for Cancer - Los Angeles, United States
Duration: 13 Aug 199818 Aug 1998

Conference

Conference8th International Symposium on Neutron Capture Therapy for Cancer
Country/TerritoryUnited States
CityLos Angeles
Period13/08/9818/08/98

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