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 › Conference article in proceedings › Scientific › peer-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 language	English
Title of host publication	Frontiers in Neutron Capture Therapy
Editors	M. F. Hawthorne, K. Shelly, R. J. Wiersema
Publisher	Springer
Pages	623-628
Volume	1
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	A4 Article in a conference publication
Event	8th International Symposium on Neutron Capture Therapy for Cancer - Los Angeles, United States Duration: 13 Aug 1998 → 18 Aug 1998

Conference

Conference	8th International Symposium on Neutron Capture Therapy for Cancer
Country	United States
City	Los Angeles
Period	13/08/98 → 18/08/98

Access to Document

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

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title = "Shielding design and calculations for the Finnish BNCT facility",

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.",

author = "Petri Kotiluoto and Pekka Hiism{\"a}ki and Iiro Auterinen and Tiina Sepp{\"a}l{\"a} and Carita Aschan",

year = "2001",

doi = "10.1007/978-1-4615-1285-1_89",

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editor = "Hawthorne, {M. F. } and K. Shelly and Wiersema, {R. J.}",

booktitle = "Frontiers in Neutron Capture Therapy",

publisher = "Springer",

address = "Germany",

note = "8th International Symposium on Neutron Capture Therapy for Cancer ; Conference date: 13-08-1998 Through 18-08-1998",

}

Kotiluoto, P, Hiismäki, P, Auterinen, I, Seppälä, T & Aschan, C 2001, Shielding design and calculations for the Finnish BNCT facility. in MF Hawthorne, K Shelly & RJ Wiersema (eds), Frontiers in Neutron Capture Therapy. vol. 1, Springer, pp. 623-628, 8th International Symposium on Neutron Capture Therapy for Cancer, Los Angeles, United States, 13/08/98. https://doi.org/10.1007/978-1-4615-1285-1_89

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

Frontiers in Neutron Capture Therapy. ed. / M. F. Hawthorne; K. Shelly; R. J. Wiersema. Vol. 1 Springer, 2001. p. 623-628.

Research output: Chapter in Book/Report/Conference proceeding › Conference article in proceedings › Scientific › peer-review

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N2 - 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.

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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