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NSR database version of May 10, 2024.

Search: Author = D.Cheneler

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2024DE05      Appl.Radiat.Isot. 205, 111146 (2024)

C.Degueldre, J.Findlay, D.Cheneler, S.Sardar, S.Green

Short life fission products extracted from molten salt reactor fuel for radiopharmaceutical applications.

RADIOACTIVITY ⁸²Br, ⁸⁶Rb, ⁹⁰Sr, ⁹⁰Y, ⁹⁹Mo, ⁹⁹Tc, ¹⁰³Rh, ¹¹¹Ag, ¹²⁷Sb, ¹²⁷Te, ^126,131I, ¹³³Xe, ¹³⁶Cs, ^141,143Ce, ¹⁴³Pr, ¹⁴⁷Nd, ¹⁴⁷Pm, ¹⁵³Sm, ¹⁵⁶Eu, ¹⁵⁹Gd, ¹⁶¹Tb(β^-); analyzed available data; deduced the potential of using short life fission product radioisotopes extracted from a molten salt reactor and their separation using specific thermodynamic and radiochemical conditions.

doi: 10.1016/j.apradiso.2023.111146
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2017MO11      Nucl.Instrum.Methods Phys.Res. B399, 48 (2017)

S.D.Monk, B.A.Shippen, B.R.Colling, D.Cheneler, H.Al Hamrashdi, T.Alton

A comparison of MCNP6-1.0 and GEANT 4-10.1 when evaluating the neutron output of a complex real world nuclear environment: The thermal neutron facility at the Tri Universities Meson facility

doi: 10.1016/j.nimb.2017.03.112
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