Abstract
A Boron Neutron Capture Therapy (BNCT) treatment facility with an epithermal neutron beam has been successfully completed at the Finnish FiR 1 TRIGA reactor at VTT, Espoo. The clinical trials on human patients were started in May 1999. The beam utilizes a specially developed moderator material FLUENTAL™ Extensive measurements and calculations have been carded out to characterize the neutron and gamma fields, both in the "free beam" and in tissue substitute phantoms. Despite the fairly low reactor power (250 kW) an epithermal fluence rate of 1.06 × 109 n cm-2 s-1 is achieved at the beam exit aperture with low fast-neutron contamination. The beam has been modeled in detail using the DORT transport code with the BUGLE-80 library. The neutron spectrum has been adjusted with the LSL-M2 code based on multiple-foil activation. Similar calculations and measurements have been performed by the Finnish BNCT team at the BMRR facility for direct comparison.
| Original language | English |
|---|---|
| Title of host publication | Reactor Dosimetry |
| Subtitle of host publication | Radiation Metrology and Assessment |
| Editors | J. Williams, D. Vehar, F. Ruddy, D. Gilliam |
| Publisher | American Society for Testing and Materials ASTM |
| Pages | 175-182 |
| ISBN (Electronic) | 978-0-8031-5450-6 |
| ISBN (Print) | 978-0-8031-2884-2 |
| DOIs | |
| Publication status | Published - 1 Jan 2001 |
| MoE publication type | A4 Article in a conference publication |
Publication series
| Series | ASTM Selected Technical Papers |
|---|---|
| Volume | 1398 |
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Keywords
- Activation detectors
- BNCT
- Epithermal neutrons
- Research reactors
- Spectrum adjustment
- Transport methods
- TRIGA reactors
Cite this
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Neutron beam characterization at the finnish BNCT facility : Measurements and calculations. / Serén, Tom; Auterinen, Iiro; Kotiluoto, Petri; Seppälä, Tiina.
Reactor Dosimetry: Radiation Metrology and Assessment. ed. / J. Williams; D. Vehar; F. Ruddy; D. Gilliam. American Society for Testing and Materials ASTM, 2001. p. 175-182 (ASTM Selected Technical Papers, Vol. 1398).Research output: Chapter in Book/Report/Conference proceeding › Conference article in proceedings › Scientific › peer-review
TY - GEN
T1 - Neutron beam characterization at the finnish BNCT facility
T2 - Measurements and calculations
AU - Serén, Tom
AU - Auterinen, Iiro
AU - Kotiluoto, Petri
AU - Seppälä, Tiina
PY - 2001/1/1
Y1 - 2001/1/1
N2 - A Boron Neutron Capture Therapy (BNCT) treatment facility with an epithermal neutron beam has been successfully completed at the Finnish FiR 1 TRIGA reactor at VTT, Espoo. The clinical trials on human patients were started in May 1999. The beam utilizes a specially developed moderator material FLUENTAL™ Extensive measurements and calculations have been carded out to characterize the neutron and gamma fields, both in the "free beam" and in tissue substitute phantoms. Despite the fairly low reactor power (250 kW) an epithermal fluence rate of 1.06 × 109 n cm-2 s-1 is achieved at the beam exit aperture with low fast-neutron contamination. The beam has been modeled in detail using the DORT transport code with the BUGLE-80 library. The neutron spectrum has been adjusted with the LSL-M2 code based on multiple-foil activation. Similar calculations and measurements have been performed by the Finnish BNCT team at the BMRR facility for direct comparison.
AB - A Boron Neutron Capture Therapy (BNCT) treatment facility with an epithermal neutron beam has been successfully completed at the Finnish FiR 1 TRIGA reactor at VTT, Espoo. The clinical trials on human patients were started in May 1999. The beam utilizes a specially developed moderator material FLUENTAL™ Extensive measurements and calculations have been carded out to characterize the neutron and gamma fields, both in the "free beam" and in tissue substitute phantoms. Despite the fairly low reactor power (250 kW) an epithermal fluence rate of 1.06 × 109 n cm-2 s-1 is achieved at the beam exit aperture with low fast-neutron contamination. The beam has been modeled in detail using the DORT transport code with the BUGLE-80 library. The neutron spectrum has been adjusted with the LSL-M2 code based on multiple-foil activation. Similar calculations and measurements have been performed by the Finnish BNCT team at the BMRR facility for direct comparison.
KW - Activation detectors
KW - BNCT
KW - Epithermal neutrons
KW - Research reactors
KW - Spectrum adjustment
KW - Transport methods
KW - TRIGA reactors
UR - http://www.scopus.com/inward/record.url?scp=0035554769&partnerID=8YFLogxK
U2 - 10.1520/STP13594S
DO - 10.1520/STP13594S
M3 - Conference article in proceedings
AN - SCOPUS:0035554769
SN - 978-0-8031-2884-2
T3 - ASTM Selected Technical Papers
SP - 175
EP - 182
BT - Reactor Dosimetry
A2 - Williams, J.
A2 - Vehar, D.
A2 - Ruddy, F.
A2 - Gilliam, D.
PB - American Society for Testing and Materials ASTM
ER -