Use of the MCNPX to calculate the neutron spectra around the GE-PETtrace 8 cyclotron of the CDTN/CNEN, Brazil-Reference-Cited by-同舟云学术

Use of the MCNPX to calculate the neutron spectra around the GE-PETtrace 8 cyclotron of the CDTN/CNEN, Brazil

Published:2014-01 Issue: Volume:83 Page:235-241
ISSN:0969-8043
Container-title:Applied Radiation and Isotopes
language:en
Short-container-title:Applied Radiation and Isotopes

Author:

Lacerda M.A.S.,Campolina D.A.M.,Guimarães A.M.,Benavente J.A.,da Silva T.A.

Publisher

Elsevier BV

Subject

Radiation

Reference31 articles.

1. Monte Carlo neutron doses estimations inside a PET Cyclotron vault room;Barquero;Radiat. Prot. Dosim,2007

2. Neutron spectrometry with Bonner spheres for area monitoring in particle accelerators;Bedogni;Radiat. Prot. Dosim,2011

3. Design and experimental validation of a Bonner sphere spectrometer based on dysprosium activation foils;Bedogni;Radiat. Meas.,2010

4. Neutron activation of air by a biomedical cyclotron and an assessment of dose to neighborhood populations;Birattari;Radiat. Prot. Dosim.,1986

5. Carroll, L R, 2002. Estimating the radiation source term for PET isotope targets. In: Proceedings of the 9th International Workshop on Targetry and Target Chemistry, (Turku, Finland, May).

Cited by 7 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. Characterization of the Direct and Scattered Neutron Flux Around Cyclotron Target;Lecture Notes in Mechanical Engineering;2024

2. Characterization of the secondary neutron field inside a cyclotron for production of radiopharmaceuticals;Applied Radiation and Isotopes;2023-09

3. MONTE CARLO SIMULATION OF THE RADIATION SOURCE TERM FROM [18O]H2O CYCLOTRON TARGET BOMBARDMENT WITH PROTONS OF 16.5 MEV;Radiation Protection Dosimetry;2023-03-13

4. Comparison of extended-range and conventional Bonner Sphere Spectrometers (BSS) in an AmBe neutron field – Applicability of the ReBUNKI unfolding code for extended-range BSS;Radiation Physics and Chemistry;2023-02

5. Characterization of the neutron flux during production of 18F at a medical cyclotron and evaluation of the incidental neutron spectrum for neutron damage studies;Applied Radiation and Isotopes;2019-12