Measurement of the 64Zn,47Ti(n,p) cross sections using a DD neutron generator for medical isotope studies

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

卷:410

Article

Voyles, A. S.¹  Basunia, M. S.²  Batchelder, J. C.¹  Bauer, J. D.³  Becker, T. A.⁴  Bernstein, L. A.^1,2  Matthews, E. F.¹  Renne, P. R.^4,5  Rutte, D.^4,5  Unzueta, M. A.¹  van Bibber, K. A.¹ 

[1] Univ Calif Berkeley, Dept Nucl Engn, Berkeley, CA 94720 USA

[2] Lawrence Berkeley Natl Lab, Berkeley, CA 94720 USA

[3] Lawrence Livermore Natl Lab, Livermore, CA 94551 USA

[4] Berkeley Geochronol Ctr, Berkeley, CA 94709 USA

[5] Univ Calif Berkeley, Dept Earth & Planetary Sci, Berkeley, CA 94720 USA

关键词: DD neutron generator;    Medical isotope production;    Scandium (Sc) and copper (Cu);    radioisotopes;    Indium;    Ratio activation;    Theranostics;   

DOI  :  10.1016/j.nimb.2017.08.021

来源: Elsevier

【 摘 要 】

Cross sections for the Ti-47(n,p)Sc-47 and Zn-64(n,p)Cu-64 reactions have been measured for quasimonoenergetic DD neutrons produced by the UC Berkeley High Flux Neutron Generator (HFNG). The HFNG is a compact neutron generator designed as a flux-trap that maximizes the probability that a neutron will interact with a sample loaded into a specific, central location. The study was motivated by interest in the production of Sc-47 and Cu-64 as emerging medical isotopes. The cross sections were measured in ratio to the In-113(n,n')In-113m and In-115(n,n')In-115m inelastic scattering reactions on co-irradiated indium samples. Post-irradiation counting using an HPGe and LEPS detectors allowed for cross section determination to within 5% uncertainty. The Zn-64(n,p)Cu-64 cross section for 2.76(-0.02)(+0.01) MeV neutrons is reported as 49.3 +/- 2.6 mb (relative to In-113) or 46.4 +/- 1.7 mb (relative to In-115), and the Ti-47(n,p)Sc-47 cross section is reported as 26.26 +/- 0.82 mb. The measured cross sections are found to be in good agreement with existing measured values but with lower uncertainty (<5%), and also in agreement with theoretical values. This work highlights the utility of compact, flux-trap DD-based neutron sources for nuclear data measurements and potentially the production of radionuclides for medical applications. (C) 2017 Elsevier B.V. All rights reserved.

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