Heavy Nuclide Cross Sections of Particular Interest to Thermal Reactor Operation: Conventions, Measurements and Preferred Values

Nuclear data for reactor production of 131Ba and 133Ba

The newest radioisotope for brachytherapy treatment of prostate cancer is ¹³¹Cs (t_1/2 = 9.69 d, 100% EC). Generated via electron capture decay of ¹³¹Ba (t_1/2 = 11.6 d, 100% EC), ¹³¹Cs has been used in brachytherapy for prostate cancer since 2004. The ¹³¹Ba parent is produced through neutron capture of enriched ¹³⁰Ba in a nuclear reactor. For large-scale production of ¹³¹Ba, an accurate knowledge of production and burnup cross sections of ¹³¹Ba are essential. In this paper, we report two group cross sections (thermal and resonance integrals) for ¹³⁰Ba and ¹³¹Ba and a new measure of the half-life of ¹³¹Ba. Targets consisting of milligram quantities of enriched ¹³⁰Ba (∼35%) were irradiated in Oak Ridge National Laboratory's High Flux Isotope Reactor at thermal and resonance neutron fluxes of (1.9-2.1) × 10¹⁵ and (5.8-7.0) × 10¹³ neutrons·cm^-2 s^-1, respectively, for durations ranging from 3 to 26 days. In addition, cadmium covered samples of ¹³⁰Ba were irradiated for 1 hour at 12.6% full reactor power (10.7 MW). The yield of ¹³¹Ba approaches a saturation value of ∼60 GBq (∼1.6 Ci) per mg of ¹³⁰Ba for 20 days irradiation at a thermal neutron flux of 1.8 × 10¹⁵ n·s^-1·cm^-2, with a thermal/epithermal ratio of ∼30. Under the above experimental conditions, the two group cross sections of ¹³⁰Ba are 6.9 ± 0.5 b (thermal, σ⁰) and 173 ± 7 b (resonance, I⁰). These values represent the sum of cross sections to metastable and ground states of ¹³¹Ba. For ¹³¹Ba, the empirically measured thermal cross section is 200 ± 50 b assuming an I⁰/σ⁰ of 10. This cross section is reported for the first time. Further, the half-life of ¹³¹Ba was remeasured to be 11.657 ± 0.008 d. Lastly, this study also resulted in the co-production of ¹³³Ba (t_1/2 = 10.52 y, 100% EC). The experimental yield of ¹³³Ba is ∼370 MBq (∼10 mCi) per mg of ¹³²Ba (thin target) for one cycle irradiation in the High Flux Isotope Reactor, and measured two-group ¹³²Ba cross sections are 7.2 ± 0.2 b and 39.9 ± 1.3 b. These values also represent the sum of cross sections to metastable and ground states of ¹³³Ba.

Neutron flux characterization of a peripheral target position in the High Flux Isotope Reactor

The High Flux Isotope Reactor at the Oak Ridge National Laboratory provides the highest steady-state thermal neutron flux in the western world for a wide range of experiments and for isotope production. The highest available fluxes are located in a flux trap region created inside the nested fuel elements. The experimentally determined thermal and the empirically obtained epithermal flux values along the vertical axis of the peripheral target position were fit to cosine curves, with the thermal flux ranging from 1.1 x 10(15)ns(-1)cm(-2) at outer positions to 1.5 x 10(15)ns(-1)cm(-2) at the center. The corresponding epithermal flux ranged from 3.5 x 10(13) to 7.5 x 10(13)ns(-1)cm(-2), respectively. The fast neutron flux (En > or = 0.32 MeV in two positions and En > or = 1.5 MeV in two other positions) was approximately 6 x 10(14)ns(-1)cm(-2), corresponding to a fast to thermal ratio of approximately 0.4.