Abstract
| 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 | |
| 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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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
TY - CHAP
T1 - Shielding design and calculations for the Finnish BNCT facility
AU - Kotiluoto, Petri
AU - Hiismäki, Pekka
AU - Auterinen, Iiro
AU - Seppälä, Tiina
AU - Aschan, Carita
PY - 2001
Y1 - 2001
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.
U2 - 10.1007/978-1-4615-1285-1_89
DO - 10.1007/978-1-4615-1285-1_89
M3 - Chapter or book article
SN - 978-1-4613-5478-9
SP - 623
EP - 628
BT - Frontiers in Neutron Capture Therapy. M. Frederick Hawthorne, Kenneth Shelly & Richard J. Wiersema (eds.). Vol. 1
A2 - Hawthorne, M. F.
A2 - Shelly, K.
A2 - Wiersema, R. J.
PB - Springer
ER -