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Program - Brookhaven National Laboratory

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channels, the only open channels. Experimental data below the Coulomb barrier are difficult to measure<br />

and for this reason are scarce. In the rare earth region and particularly for the Samarium isotopes, there<br />

are insufficient experimental data. In this work, the cross sections of (p,gamma) and (p,n) processes on<br />

147,149 Sm were measured by gamma ray spectroscopy using the activation method. Proton beams of energies<br />

between 3.5-8 MeV provided by the IFIN-HH Tandem accelerator, bombarded stacks of 147,149 Sm thin<br />

targets. The induced activity was measured with a pair of large volume HPGe detectors in close geometry<br />

in a special low background shielded area[1], thus allowing absolute cross section measurements down to<br />

tens of microbarns. The results are compared with the predictions of the Hauser-Feshbach statistical model<br />

calculations performed with the code EMPIRE 3.1 Rivoli. Different sets of optical model parameters were<br />

used in the calculations.<br />

[1] D. Filipescu et al., “Cross sections for α-particle induced reactions on 115,116 Sn around the Coulomb<br />

barrier,” Phys. Rev. C 83, 064609 (2011)<br />

Session DC Evaluated Nuclear Data Libraries<br />

Monday March 4, 2013<br />

Room: Empire East at 3:30 PM<br />

DC 1 3:30 PM<br />

New Version of Chinese Evaluated Nuclear Data Library CENDL-3.2 and the Development<br />

Methodology of Nuclear Data Evaluation in China<br />

Ge Zhigang, Wu Haicheng, Cheng Guochang, Xu Ruirui, Huang Xiaolong, Shu Nengchuan, Qian Jing,<br />

Liu Ping<br />

China Committee of Nuclear Data, China Nuclear Data Center, China Institute of Atomic Energy,<br />

P.O.Box 275-1, Beijing 102413, P.R.China, Fax:+86-10-69358119<br />

The CENDL-3.2 is general purpose evaluated nuclear data file which consists of the neutron reactions sublibrary,<br />

the activation sub-library, decay data sub-library and fission yields sub-library. CENDL-3.2 can be<br />

used for the nuclear engineering, nuclear medicine and nuclear science etc. fields. The CENDL-3.2 is based<br />

on the previous version of CENDL and other special purpose libraries established by China Nuclear Data<br />

Center(CNDC), the updated experimental information and new nuclear data evaluation methodologies.<br />

The mainly contribution of CENDL-3.2 are being carried out at CNDC, China Institute of Atomic Energy<br />

and China Nuclear Data Coordination Network(CNDCN). The nuclei region of the new neutron reactions<br />

sub-library will be extend comparison with the CENDL-3.1 and the materials number will up to 300, which<br />

can be covered almost needs for the nuclear engineering, nuclear power and related fields. The high fidelity<br />

covariance files for some important structural materials, actinide and low fidelity covariance files for other<br />

nuclei will be included in the sub-library. All the covariance files will be evaluated through a covariance<br />

evaluation system COVAC developed by CNDC. The benchmark testing and validation for the CENDL-3.2<br />

will be performed through the updated Evaluated Nuclear Data Integra Test System (ENDIST) established<br />

at CNDC. Activation sub-library will contain the most important excitation functions for more than 600<br />

nuclei which can be used for nuclear reactor design, operation and nuclear safety etc. Some of the evaluated<br />

data will be obtained based on the updated measurements and mode calculations. Decay data sub-library<br />

contains the updated decay information for more than 2000 nuclei, and more than 200 new evaluations<br />

will be carried out by Chinese evaluators, other the data come from the new results of the NSDD. Fission<br />

product yield sub-library will provide the evaluated fission yields by various methods for the neutron<br />

introduced fissions for the U, Pu and Th etc. The progress of the evaluation methodologies during recent<br />

years at CNDC and CNDCN will be introduced in this presentation.<br />

61

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