GE PETtrace cyclotron as a neutron source for boron neutron capture therapy

Bosko, A.; Zhilchenkov, D; Reece, W.D.

doi:10.1016/j.apradiso.2004.05.076

Cited by 9 publications

(17 citation statements)

References 9 publications

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“…The total physical dose in BNCT consists of the gamma dose (D g ), the fast neutrons dose (D f ), the thermal neutron dose (DN) and the boron dose (DB) as shown below (IAEA, 2001;Bosko, 2005;Durisi, 2005;Turcotte, 2004). …”

Section: Dose Components In Bnctmentioning

confidence: 99%

“…Therefore the relation between the physical dose and the biological dose can be written as (IAEA, 2001;Bosko, 2005;Durisi, 2005;Turcotte, 2004): where D g , D f , DN and DB are the physical dose components, whereas the w g , w n and w B are the weighing factors and D w is the biological weighted dose.…”

Section: Dose Components In Bnctmentioning

confidence: 99%

“…The skull bone and skin were taken separately from the brain tissue. The tumor volumes were taken as spheres with 0.50 cm diameter at the depths of 1.0, 2.0, 3.0, 4.0, 5.0, 6.0, 7.0, 8.0, 9.0 and 10.0 cm inside the phantom brain (Bosko, 2005).…”

Section: The Phantom Brainmentioning

confidence: 99%

“…(1) and (2). These heavy particles locally deposit their energy of 2.34 MeV in a range of (5e9) mm, which corresponds to the cell diameter (Kotiluoto and Auterinen, 2004;Durisi, 2005;Bosko, 2005). By having a suitable non-toxic carrier agent for 10 B isotope that accumulates into tumor cells and a sufficient thermal flux distribution at tumor site, the tumor cell dose can be drastically boosted compared to the healthy tissue dose (Durisi, 2005;Barth et al, 2005;Sweezy, 2002).…”

Section: Introductionmentioning

confidence: 97%

“…This therapy is expected to be very effective for several types of cancers such as a malignant brain tumoreglioblastoma multiforme, for which no successful treatment has been developed. Now, worldwide research by using research reactors, accelerators and neutron generators is ongoing (IAEA, 2001;Bosko, 2005;Binns et al, 2002;Montagnini et al, 2002;Durisi, 2005;Auterinen et al, 2004;Liu et al, 2004).…”

Section: Introductionmentioning

confidence: 98%

See 4 more Smart Citations

Design calculation of an epithermal neutronic beam for BNCT at the Syrian MNSR using the MCNP4C code

Shaaban

Albarhoum

2015

Progress in Nuclear Energy

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Section: Dose Components In Bnctmentioning

confidence: 99%

Section: Dose Components In Bnctmentioning

confidence: 99%

Section: The Phantom Brainmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 97%

Section: Introductionmentioning

confidence: 98%

See 3 more Smart Citations

Design calculation of an epithermal neutronic beam for BNCT at the Syrian MNSR using the MCNP4C code

Shaaban

Albarhoum

2015

Progress in Nuclear Energy

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A study of the simulation of the influence on formed neutron spectrum when Li target was covered with polyimide protective film

Ganjeh

Eslami

2018

J Radioanal Nucl Chem

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Source terms, shielding calculations and soil activation for a medical cyclotron

Konheiser¹,

Naumann²,

Ferrari³

et al. 2016

J. Radiol. Prot.

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Calculations of the shielding and estimates of soil activation for a medical cyclotron are presented in this work. Based on the neutron source term from the O(p,n)F reaction produced by a 28 MeV proton beam, neutron and gamma dose rates outside the building were estimated with the Monte Carlo code MCNP6 (Goorley et al 2012 Nucl. Technol. 180 298-315). The neutron source term was calculated with the MCNP6 code and FLUKA (Ferrari et al 2005 INFN/TC_05/11, SLAC-R-773) code as well as with supplied data by the manufacturer. MCNP and FLUKA calculations yielded comparable results, while the neutron yield obtained using the manufacturer-supplied information is about a factor of 5 smaller. The difference is attributed to the missing channels in the manufacturer-supplied neutron source terms which considers only the O(p,n)F reaction, whereas the MCNP and FLUKA calculations include additional neutron reaction channels. Soil activation was performed using the FLUKA code. The estimated dose rate based on MCNP6 calculations in the public area is about 0.035 µSv h and thus significantly below the reference value of 0.5 µSv h (2011 Strahlenschutzverordnung, 9 Auflage vom 01.11.2011, Bundesanzeiger Verlag). After 5 years of continuous beam operation and a subsequent decay time of 30 d, the activity concentration of the soil is about 0.34 Bq g.

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GE PETtrace cyclotron as a neutron source for boron neutron capture therapy

Cited by 9 publications

References 9 publications

Design calculation of an epithermal neutronic beam for BNCT at the Syrian MNSR using the MCNP4C code

Design calculation of an epithermal neutronic beam for BNCT at the Syrian MNSR using the MCNP4C code

A study of the simulation of the influence on formed neutron spectrum when Li target was covered with polyimide protective film

Source terms, shielding calculations and soil activation for a medical cyclotron

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