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Neutron flux and gamma dose measurement in the BNCT irradiation facility at the TRIGA reactor of the University of Pavia.

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Title: Neutron flux and gamma dose measurement in the BNCT irradiation facility at the TRIGA reactor of the University of Pavia.
Authors: Bortolussi, S.1,2 silva.bortolussi@unipv.it, Protti, N.2, Ferrari, M.2,3, Postuma, I.2, Fatemi, S.1,2, Prata, M.2,4, Ballarini, F.1,2, Carante, M.P.1,2, Farias, R.5,6, González, S.J.5,6, Marrale, M.7,8,9, Gallo, S.10,11, Bartolotta, A.7,8, Iacoviello, G.12, Nigg, D.13, Altieri, S.1,2
Source: Nuclear Instruments & Methods in Physics Research Section B. Jan2018, Vol. 414, p113-120. 8p.
Subjects: Neutron flux, Boron-neutron capture therapy, Nuclear reactors, Universita di Pavia, Irradiation
Abstract: University of Pavia is equipped with a TRIGA Mark II research nuclear reactor, operating at a maximum steady state power of 250 kW. It has been used for many years to support Boron Neutron Capture Therapy (BNCT) research. An irradiation facility was constructed inside the thermal column of the reactor to produce a sufficient thermal neutron flux with low epithermal and fast neutron components, and low gamma dose. In this irradiation position, the liver of two patients affected by hepatic metastases from colon carcinoma were irradiated after borated drug administration. The facility is currently used for cell cultures and small animal irradiation. Measurements campaigns have been carried out, aimed at characterizing the neutron spectrum and the gamma dose component. The neutron spectrum has been measured by means of multifoil neutron activation spectrometry and a least squares unfolding algorithm; gamma dose was measured using alanine dosimeters. Results show that in a reference position the thermal neutron flux is ( 1.20 ± 0.03 ) × 10 10  cm −2  s −1 when the reactor is working at the maximum power of 250 kW, with the epithermal and fast components, respectively, 2 and 3 orders of magnitude lower than the thermal component. The ratio of the gamma dose with respect to the thermal neutron fluence is 1.2 × 10 - 13  Gy/(n/cm 2 ). [ABSTRACT FROM AUTHOR]
Copyright of Nuclear Instruments & Methods in Physics Research Section B is the property of Elsevier B.V. and its content may not be copied or emailed to multiple sites without the copyright holder's express written permission. Additionally, content may not be used with any artificial intelligence tools or machine learning technologies. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
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  Data: Neutron flux and gamma dose measurement in the BNCT irradiation facility at the TRIGA reactor of the University of Pavia.
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  Data: <searchLink fieldCode="AR" term="%22Bortolussi%2C+S%2E%22">Bortolussi, S.</searchLink><relatesTo>1,2</relatesTo><i> silva.bortolussi@unipv.it</i><br /><searchLink fieldCode="AR" term="%22Protti%2C+N%2E%22">Protti, N.</searchLink><relatesTo>2</relatesTo><br /><searchLink fieldCode="AR" term="%22Ferrari%2C+M%2E%22">Ferrari, M.</searchLink><relatesTo>2,3</relatesTo><br /><searchLink fieldCode="AR" term="%22Postuma%2C+I%2E%22">Postuma, I.</searchLink><relatesTo>2</relatesTo><br /><searchLink fieldCode="AR" term="%22Fatemi%2C+S%2E%22">Fatemi, S.</searchLink><relatesTo>1,2</relatesTo><br /><searchLink fieldCode="AR" term="%22Prata%2C+M%2E%22">Prata, M.</searchLink><relatesTo>2,4</relatesTo><br /><searchLink fieldCode="AR" term="%22Ballarini%2C+F%2E%22">Ballarini, F.</searchLink><relatesTo>1,2</relatesTo><br /><searchLink fieldCode="AR" term="%22Carante%2C+M%2EP%2E%22">Carante, M.P.</searchLink><relatesTo>1,2</relatesTo><br /><searchLink fieldCode="AR" term="%22Farias%2C+R%2E%22">Farias, R.</searchLink><relatesTo>5,6</relatesTo><br /><searchLink fieldCode="AR" term="%22González%2C+S%2EJ%2E%22">González, S.J.</searchLink><relatesTo>5,6</relatesTo><br /><searchLink fieldCode="AR" term="%22Marrale%2C+M%2E%22">Marrale, M.</searchLink><relatesTo>7,8,9</relatesTo><br /><searchLink fieldCode="AR" term="%22Gallo%2C+S%2E%22">Gallo, S.</searchLink><relatesTo>10,11</relatesTo><br /><searchLink fieldCode="AR" term="%22Bartolotta%2C+A%2E%22">Bartolotta, A.</searchLink><relatesTo>7,8</relatesTo><br /><searchLink fieldCode="AR" term="%22Iacoviello%2C+G%2E%22">Iacoviello, G.</searchLink><relatesTo>12</relatesTo><br /><searchLink fieldCode="AR" term="%22Nigg%2C+D%2E%22">Nigg, D.</searchLink><relatesTo>13</relatesTo><br /><searchLink fieldCode="AR" term="%22Altieri%2C+S%2E%22">Altieri, S.</searchLink><relatesTo>1,2</relatesTo>
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  Data: <searchLink fieldCode="JN" term="%22Nuclear+Instruments+%26+Methods+in+Physics+Research+Section+B%22">Nuclear Instruments & Methods in Physics Research Section B</searchLink>. Jan2018, Vol. 414, p113-120. 8p.
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  Data: University of Pavia is equipped with a TRIGA Mark II research nuclear reactor, operating at a maximum steady state power of 250 kW. It has been used for many years to support Boron Neutron Capture Therapy (BNCT) research. An irradiation facility was constructed inside the thermal column of the reactor to produce a sufficient thermal neutron flux with low epithermal and fast neutron components, and low gamma dose. In this irradiation position, the liver of two patients affected by hepatic metastases from colon carcinoma were irradiated after borated drug administration. The facility is currently used for cell cultures and small animal irradiation. Measurements campaigns have been carried out, aimed at characterizing the neutron spectrum and the gamma dose component. The neutron spectrum has been measured by means of multifoil neutron activation spectrometry and a least squares unfolding algorithm; gamma dose was measured using alanine dosimeters. Results show that in a reference position the thermal neutron flux is ( 1.20 ± 0.03 ) × 10 10  cm −2  s −1 when the reactor is working at the maximum power of 250 kW, with the epithermal and fast components, respectively, 2 and 3 orders of magnitude lower than the thermal component. The ratio of the gamma dose with respect to the thermal neutron fluence is 1.2 × 10 - 13  Gy/(n/cm 2 ). [ABSTRACT FROM AUTHOR]
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  Data: <i>Copyright of Nuclear Instruments & Methods in Physics Research Section B is the property of Elsevier B.V. and its content may not be copied or emailed to multiple sites without the copyright holder's express written permission. Additionally, content may not be used with any artificial intelligence tools or machine learning technologies. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract.</i> (Copyright applies to all Abstracts.)
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