Program - Brookhaven National Laboratory
Program - Brookhaven National Laboratory
Program - Brookhaven National Laboratory
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PA 1 3:30 PM<br />
Investigation of Neutron-Induced Reactions at n TOF: Overview of the 2009-2012<br />
Experimental <strong>Program</strong><br />
Carlos Guerrero, on behalf of the n TOF Collaboration<br />
CERN<br />
The neutron time-of-flight facility n TOF is operating at CERN (Switzerland) since 2001, having started in<br />
2009 the second phase (n TOF-Ph2) with an upgraded spallation target. Since then, the ambitious program<br />
carried out includes a large number of experiments in the fields of nuclear technology, astrophysics, basic<br />
physics, detector development and medical applications. Following a brief description of the n TOF facility<br />
and its characteristics, the physics program at n TOF will be discussed and a detailed summary of the<br />
measurements performed between 2009 and 2012 will be presented. Special attention will be given to<br />
those experiments that have been most challenging, are more important for a particular field, have reached<br />
unprecedented levels of accuracy, or have been carried out for the first time ever.<br />
PA 2 4:00 PM<br />
Analysis of 241 Am(n,γ) Cross Section with C6D6 Detectors at the n TOF facility (CERN)<br />
K. Fraval, the n TOF collaboration<br />
CEA Saclay, Irfu, F-91191 Gif sur Yvette - France<br />
The interest for nuclear data in the actinide region is constantly renewed by the reactor physics community,<br />
both for generation IV reactor designs or transmutation studies. Indeed the NEA has placed several minor<br />
actinides, including 241 Am, on its High Priority Request List for cross section measurements. In this<br />
context, and as a part of the FP7-ANDES project, the (n,γ) reaction yield of 241 Am has been measured in<br />
2010 at the n TOF facility at CERN. The method used was time-of-flight (TOF) spectrometry, and two<br />
C6D6 scintillators were used for gamma-ray detection. The discussion will focus on detection efficiency,<br />
background estimation, and normalization. The R-matrix resonance analysis in the resolved resonance<br />
region (RRR) will then be detailed, and will be compared to current evaluations and previous data.<br />
Significant improvement, mostly through the extension of the RRR from 150 eV to 300 eV has been<br />
possible. Level densities and neutron strength functions extraction through a statistical analysis will be<br />
presented. Finally, the unresolved resonance region analysis, based on an ensemble average of the R-Matrix<br />
expressions, will be exposed, and compared to recent evaluations and previous work.<br />
PA 3 4:20 PM<br />
Neutron Capture Cross Section of 239 Pu<br />
S. Mosby, C. Arnold, T. A. Bredeweg, A. Couture, M. Jandel, J. M. Odonnell, G. Rusev, J. L. Ullmann<br />
LANL<br />
A. Chyzh, J. M. Gostic, R. A. Henderson, E. Kwan, C-Y. Wu<br />
LLNL<br />
High fidelity measurements of 239 Pu(n, γ) are required for both nuclear energy campaigns and improved<br />
understanding of reaction diagnostics for defense programs. As part of the Advanced Reactor Concepts<br />
(ARC) program, a new design of reactors is being considered for safe and cost-effective use in the United<br />
States and around the world. While traditional reactor designs have relied on light water reactors, the<br />
reactors planned for ARC will have a fast neutron spectrum, requiring improved nuclear data in the keV<br />
218
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