Shielding design and calculations for the Finnish BNCT facility

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

doi:10.1007/978-1-4615-1285-1_89

Shielding design and calculations for the Finnish BNCT facility

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

VTT Technical Research Centre of Finland

Research output: Chapter in Book/Report/Conference proceeding › Chapter or book article › Professional

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 language	English
Title of host publication	Frontiers in Neutron Capture Therapy. M. Frederick Hawthorne, Kenneth Shelly & Richard J. Wiersema (eds.). Vol. 1
Editors	M. F. Hawthorne, K. Shelly, R. J. Wiersema
Publisher	Springer
Pages	623-628
ISBN (Electronic)	978-1-4615-1285-1
ISBN (Print)	978-1-4613-5478-9
DOIs	https://doi.org/10.1007/978-1-4615-1285-1_89
Publication status	Published - 2001
MoE publication type	D2 Article in professional manuals or guides or professional information systems or text book material

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Kotiluoto, P., Hiismäki, P., Auterinen, I., Seppälä, T., & Aschan, C. (2001). Shielding design and calculations for the Finnish BNCT facility. In M. F. Hawthorne, K. Shelly, & R. J. Wiersema (Eds.), Frontiers in Neutron Capture Therapy. M. Frederick Hawthorne, Kenneth Shelly & Richard J. Wiersema (eds.). Vol. 1 (pp. 623-628). Springer. https://doi.org/10.1007/978-1-4615-1285-1_89

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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.",

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Shielding design and calculations for the Finnish BNCT facility. / Kotiluoto, Petri; Hiismäki, Pekka; Auterinen, Iiro; Seppälä, Tiina; Aschan, Carita.

Frontiers in Neutron Capture Therapy. M. Frederick Hawthorne, Kenneth Shelly & Richard J. Wiersema (eds.). Vol. 1. ed. / M. F. Hawthorne; K. Shelly; R. J. Wiersema. Springer, 2001. p. 623-628.

Research output: Chapter in Book/Report/Conference proceeding › Chapter or book article › Professional

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AB - 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.

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10.1007/978-1-4615-1285-1_89