Optimization of the target of an accelerator-driven neutron source through Monte Carlo numerical simulation of neutron and gamma transport by the PRIZMA code

Author:

Kandiev Ya.,Kashaeva E.,Malyshkin G.,Bayanov B.,Taskaev S.

Publisher

Elsevier BV

Subject

Radiation

Reference13 articles.

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2. Aleynik, V., Bayanov, B., Burdakov, A., et al., 2011. New technical solution for use the time-of-flight technique to measure neutron spectra. Appl. Radiat. Isot. (this issue).

3. Monte-Carlo simulation in nuclear geophysics: comparison of the PRIZMA Monte Carlo program and benchmark experiments;Arnautova;Nucl. Geophys.,1993

4. Accelerator-based neutron source for the neutron-capture and fast neutron therapy at hospital;Bayanov;Nucl. Instr. Meth. Phys. Res. A,1998

5. Neutron producing target for accelerator based neutron capture therapy;Bayanov;J. Phys.,2006

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