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Program - Brookhaven National Laboratory

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and neutron multiplicity, information about the prompt neutron and γ-ray distributions as a function of<br />

incident neutron energy is limited. Only a handful of data is available, mostly at thermal energies, on the<br />

prompt γ-ray distributions. The prompt γ-ray and neutron distributions for the spontaneous fission of<br />

252 Cf and neutron-induced fission of 235 U at incident energies of 1-20 MeV were measured simultaneously<br />

[1] using an EJ301 liquid scintillator detector array [2] at the WNR/LANSCE facility. The feasibility of<br />

exacting information about the prompt neutron and γ-ray distributions by using the same detector opens<br />

up the opportunity to study γ-neutron correlations while simultaneously reducing amount of scattering<br />

material. The first step in achieving this goal was to determine whether we could unfold the γ-ray and<br />

neutron spectra. The prompt γ-ray spectra were unfolded using a simulated detector response matrix<br />

validated using standard calibration sources. The γ-ray distributions obtained using the iterative Bayesian<br />

and singular value decomposition unfolding techniques and comparisons to previous measurements will be<br />

presented. This work benefited from the use of the LANSCE accelerator facility and was performed under<br />

the auspices of the U.S. DOE by LLNL under Contract DE-AC52-07NA27344 and LANL under Contract<br />

DE-AC52-06NA25396.<br />

[1] E. Kwan et al., Nucl. Instrum. Methods Phys. Res. A 688, 555 (2012). [2] D. Rochman et al., Nucl.<br />

Instrum. Methods Phys. Res. A 523, 102 (2004).<br />

GF 3 2:20 PM<br />

Cross Section Measurements of the Radioactive 107 Pd and Stable 105,108 Pd nuclei<br />

S. Nakamura, A. Kimura, F. Kitatani, M. Ohta, K. Furutaka, S. Goko, K.Y.Hara, H. Harada, T. Kin, M.<br />

Koizumi, M. Oshima, and Y. Toh<br />

Nuclear Science and Engineering Directorate, Japan Atomic Energy Agency, Tokai-mura, Naka-gun,<br />

Ibaraki, 319-1195, Japan<br />

K. Kino, F. Hiraga, T. Kamiyama, and Y. Kiyanagi<br />

Graduate School of Engineering, Hokkaido University, Kita-13, Nishi-8, Kita-ku, Sapporo 060-8628,<br />

Japan<br />

T. Katabuchi, M. Mizumoto, and M. Igashira<br />

Research <strong>Laboratory</strong> for Nuclear Reactors, Tokyo Institute of Technology, 2-12-1 O-okayama, Meguro-ku,<br />

Tokyo 152-8550, Japan<br />

J. Hori, T. Fujii, S. Fukutani,and K. Takamiya<br />

Research Reactor Institute, Kyoto University, Kumatori-cho, Sennan-gun, Osaka, 590-0404, Japan<br />

Neutron-capture cross sections of Long-Lived Fission Products (LLFPs) are of great importance for predicting<br />

long-term characteristics of nuclear reactors. Palladium-107 is one of the important LLFPs because of<br />

its extremely long half-life (6.5x10 6 year) and fission yield (3% for 239 Pu). Some Pd isotopes among LLFPs,<br />

e.g. 105,108 Pd, are also listed as important absorbers for thermal and fast reactors. From these points of view,<br />

we have started the measurements of the neutron-capture cross sections for stable 105,108 Pd nuclei as well<br />

as the radioactive 107 Pd. The neutron-capture cross-section measurements by the time-of-flight method<br />

were performed using an apparatus called “Accurate Neutron-Nucleus Reaction measurement Instrument<br />

(ANNRI)” installed at the neutron Beam Line No.4 of the Materials and Life science experimental Facility<br />

(MLF) in the J-PARC. The neutron-capture cross sections of 107 Pd and 105,108 Pd have been measured in<br />

the neutron energy range from thermal to 300 eV. Some new information was obtained for resonances of<br />

these Pd nuclei. In this talk, we will present results of these measurements at J-PARC/MLF/ANNRI.<br />

Present study is the result of “Study on nuclear data by using a high intensity pulsed neutron source for<br />

advanced nuclear system” entrusted to Hokkaido University by the Ministry of Education, Culture, Sports,<br />

Science and Technology of Japan (MEXT). This work was supported by JSPS KAKENHI Grant Number<br />

22226016.<br />

102

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