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Program - Brookhaven National Laboratory

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DC 5 5:00 PM<br />

Thermal Neutron Cross Section Libraries for Silicon and Sapphire<br />

F. Cantargi, J.R. Granada<br />

Centro Atómico Bariloche and Instituto Balseiro (Comision Nacional de Energia Atomica)<br />

Techniques such as neutron radiography, prompt gamma analysis and neutron diffractometry, use thermal<br />

beams extracted from research nuclear reactors. In general, in low and medium power reactors where<br />

there are no neutron guides, beams have high components of epithermal and fast neutrons and require<br />

large shieldings. The employment of neutron filters improves the performance of these research facilities.<br />

Typical materials that are used as a neutron filters are silicon and Al2O3 which is known as sapphire when<br />

its structure is of the corundum type. Single crystals of these two materials are good neutron filters because<br />

the dependence of their inelastic scattering cross section on neutron energy is such that fast neutrons and<br />

most of the gamma radiation can be removed from the incident beam. Thermal cross section libraries at<br />

room temperature for single crystals of sapphire and silicon were generated in ENDF and ACE format<br />

using the NJOY nuclear data processing system. In both cases, a Debye spectrum was used to feed the<br />

LEAPR module of NJOY. These cross sections were validated by comparing them with experimental cross<br />

sections measured at the 25 MeV e − -LINAC based pulsed neutron source at Centro Atómico Bariloche.<br />

Good agreement between calculations and experimental data was found for both neutron filters.<br />

DC 6 5:15 PM<br />

Neutron Cross Section Evaluation of Tantalum and Tungsten<br />

Hyeong Il Kim, Cheol Woo Lee, and Young-Ouk Lee<br />

Korea Atomic Energy Research Institute<br />

The evaluation of neutron cross sections and covariances is presented for tungsten and tantalum which are<br />

considered as a prime candidate of plasma facing materials in fusion reactors and/or a structural material<br />

of Korea Helium Cooled Ceramic Reflector (HCCR) Test Blanket Module (TBM). The neutron cross<br />

sections and energy and/or angular dependent neutron spectra from existing libraries such as ENDF/B-<br />

VII.1, JENDL-4.0 and JEFF-3.1 show some discrepancies with the measured data available for tungsten<br />

and tantalum. Moreover, the integral tests of neutron production from these libraries failed to reproduce<br />

the leakage neutron measurements of OKTAVIAN. In response to these situations, the neutron cross<br />

sections for 181 Ta and 180,182,183,184,186 W were newly evaluated and compared with the existing libraries<br />

and the measured data available. This work aims at providing the reliable evaluation data and their<br />

covariances above resonance region rather than a full energy range from 10 −5 eV to 20 MeV. The thermal<br />

and resonance data were taken from the ENDF/B-VII.1, while the data above resonance region have been<br />

calculated by using the EMPIRE code system that has been used to provide a number of consistent and<br />

complete evaluations. The covariance data were generated through the KALMAN filtering implemented<br />

in the EMPIRE system, which use the sensitivity matrices by variations of model parameters and the<br />

available measurements.<br />

DC 7 5:30 PM<br />

New Resolved Resonance Region Evaluations for 63 Cu and 65 Cu to Support Nuclear<br />

Criticality Safety Analyses<br />

V. Sobes, B. Forget<br />

64

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