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

Maurizio Marrale, Antonio Bartolotta, Salvatore Gallo, Prata, Altieri, Bortolussi, Marrale, Protti, Farias, Postuma, Carante, Fatemi, Salvatore Gallo, Bartolotta, Ferrari, Giuseppina Iacoviello, Nigg, González, Ballarini

Research output: Contribution to journalArticle

5 Citations (Scopus)

Abstract

University of Pavia is equipped with a TRIGA Mark II research nuclear reactor, operating at a maximum steadystate 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 sufficientthermal neutron flux with low epithermal and fast neutron components, and low gamma dose. In this irradiationposition, the liver of two patients affected by hepatic metastases from colon carcinoma were irradiated afterborated 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 thegamma dose component. The neutron spectrum has been measured by means of multifoil neutron activationspectrometry 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) × 1010 cm−2 s−1 when thereactor is working at the maximum power of 250 kW, with the epithermal and fast components, respectively, 2and 3 orders of magnitude lower than the thermal component. The ratio of the gamma dose with respect to thethermal neutron fluence is 1.2 × 10−13 Gy/(n/cm2).
Original languageEnglish
Pages (from-to)113-120
Number of pages8
JournalNUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH. SECTION B, BEAM INTERACTIONS WITH MATERIALS AND ATOMS
Volume414
Publication statusPublished - 2017

Fingerprint

Neutron flux
flux (rate)
Dosimetry
Boron
therapy
Neutrons
boron
reactors
Irradiation
neutrons
dosage
irradiation
neutron spectra
nuclear reactors
metastasis
alanine
fast neutrons
thermal neutrons
liver
dosimeters

All Science Journal Classification (ASJC) codes

  • Nuclear and High Energy Physics
  • Instrumentation

Cite this

Neutron flux and gamma dose measurement in the BNCT irradiation facility at the TRIGA reactor of the University of Pavia. / Marrale, Maurizio; Bartolotta, Antonio; Gallo, Salvatore; Prata; Altieri; Bortolussi; Marrale; Protti; Farias; Postuma; Carante; Fatemi; Gallo, Salvatore; Bartolotta; Ferrari; Iacoviello, Giuseppina; Nigg; González; Ballarini.

In: NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH. SECTION B, BEAM INTERACTIONS WITH MATERIALS AND ATOMS, Vol. 414, 2017, p. 113-120.

Research output: Contribution to journalArticle

Marrale, M, Bartolotta, A, Gallo, S, Prata, Altieri, Bortolussi, Marrale, Protti, Farias, Postuma, Carante, Fatemi, Gallo, S, Bartolotta, Ferrari, Iacoviello, G, Nigg, González & Ballarini 2017, 'Neutron flux and gamma dose measurement in the BNCT irradiation facility at the TRIGA reactor of the University of Pavia', NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH. SECTION B, BEAM INTERACTIONS WITH MATERIALS AND ATOMS, vol. 414, pp. 113-120.
Marrale, Maurizio ; Bartolotta, Antonio ; Gallo, Salvatore ; Prata ; Altieri ; Bortolussi ; Marrale ; Protti ; Farias ; Postuma ; Carante ; Fatemi ; Gallo, Salvatore ; Bartolotta ; Ferrari ; Iacoviello, Giuseppina ; Nigg ; González ; Ballarini. / Neutron flux and gamma dose measurement in the BNCT irradiation facility at the TRIGA reactor of the University of Pavia. In: NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH. SECTION B, BEAM INTERACTIONS WITH MATERIALS AND ATOMS. 2017 ; Vol. 414. pp. 113-120.
@article{ebe2c239ae194ba2a4b1c1102870fc74,
title = "Neutron flux and gamma dose measurement in the BNCT irradiation facility at the TRIGA reactor of the University of Pavia",
abstract = "University of Pavia is equipped with a TRIGA Mark II research nuclear reactor, operating at a maximum steadystate 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 sufficientthermal neutron flux with low epithermal and fast neutron components, and low gamma dose. In this irradiationposition, the liver of two patients affected by hepatic metastases from colon carcinoma were irradiated afterborated 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 thegamma dose component. The neutron spectrum has been measured by means of multifoil neutron activationspectrometry 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) × 1010 cm−2 s−1 when thereactor is working at the maximum power of 250 kW, with the epithermal and fast components, respectively, 2and 3 orders of magnitude lower than the thermal component. The ratio of the gamma dose with respect to thethermal neutron fluence is 1.2 × 10−13 Gy/(n/cm2).",
author = "Maurizio Marrale and Antonio Bartolotta and Salvatore Gallo and Prata and Altieri and Bortolussi and Marrale and Protti and Farias and Postuma and Carante and Fatemi and Salvatore Gallo and Bartolotta and Ferrari and Giuseppina Iacoviello and Nigg and Gonz{\'a}lez and Ballarini",
year = "2017",
language = "English",
volume = "414",
pages = "113--120",
journal = "NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH. SECTION B, BEAM INTERACTIONS WITH MATERIALS AND ATOMS",
issn = "0168-583X",

}

TY - JOUR

T1 - Neutron flux and gamma dose measurement in the BNCT irradiation facility at the TRIGA reactor of the University of Pavia

AU - Marrale, Maurizio

AU - Bartolotta, Antonio

AU - Gallo, Salvatore

AU - Prata, null

AU - Altieri, null

AU - Bortolussi, null

AU - Marrale, null

AU - Protti, null

AU - Farias, null

AU - Postuma, null

AU - Carante, null

AU - Fatemi, null

AU - Gallo, Salvatore

AU - Bartolotta, null

AU - Ferrari, null

AU - Iacoviello, Giuseppina

AU - Nigg, null

AU - González, null

AU - Ballarini, null

PY - 2017

Y1 - 2017

N2 - University of Pavia is equipped with a TRIGA Mark II research nuclear reactor, operating at a maximum steadystate 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 sufficientthermal neutron flux with low epithermal and fast neutron components, and low gamma dose. In this irradiationposition, the liver of two patients affected by hepatic metastases from colon carcinoma were irradiated afterborated 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 thegamma dose component. The neutron spectrum has been measured by means of multifoil neutron activationspectrometry 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) × 1010 cm−2 s−1 when thereactor is working at the maximum power of 250 kW, with the epithermal and fast components, respectively, 2and 3 orders of magnitude lower than the thermal component. The ratio of the gamma dose with respect to thethermal neutron fluence is 1.2 × 10−13 Gy/(n/cm2).

AB - University of Pavia is equipped with a TRIGA Mark II research nuclear reactor, operating at a maximum steadystate 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 sufficientthermal neutron flux with low epithermal and fast neutron components, and low gamma dose. In this irradiationposition, the liver of two patients affected by hepatic metastases from colon carcinoma were irradiated afterborated 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 thegamma dose component. The neutron spectrum has been measured by means of multifoil neutron activationspectrometry 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) × 1010 cm−2 s−1 when thereactor is working at the maximum power of 250 kW, with the epithermal and fast components, respectively, 2and 3 orders of magnitude lower than the thermal component. The ratio of the gamma dose with respect to thethermal neutron fluence is 1.2 × 10−13 Gy/(n/cm2).

UR - http://hdl.handle.net/10447/254664

M3 - Article

VL - 414

SP - 113

EP - 120

JO - NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH. SECTION B, BEAM INTERACTIONS WITH MATERIALS AND ATOMS

JF - NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH. SECTION B, BEAM INTERACTIONS WITH MATERIALS AND ATOMS

SN - 0168-583X

ER -