Program - Brookhaven National Laboratory

section of 241 Am was deduced for a neutron energy region between 0.01 and 20 eV. The obtained cross
section and the Westcott factor are compared with the preceding experiments and evaluated values. This
work was supported by JSPS KAKENHI Grant Number 22226016.
NA 2 11:00 AM
Neutron-Induced Cross Sections Measurements Of Calcium
K. H. Guber, Oak Ridge National Laboratory, P.O. Box 2008, Oak Ridge, TN 37831, USA. S. Kopecky,
Nuclear Physics Unit, EC-JRC-IRMM, Retieseweg 111, 2440 Geel, Belgium. P. Schillebeeckx, Nuclear
Physics Unit, EC-JRC-IRMM, Retieseweg 111, 2440 Geel, Belgium. K. Kauwenberghs, Nuclear Physics
Unit, EC-JRC-IRMM, Retieseweg 111, 2440 Geel, Belgium. P. Siegler, Nuclear Physics Unit,
EC-JRC-IRMM, Retieseweg 111, 2440 Geel, Belgium.
Among its many applications, calcium is a constituent of concrete and is very frequently found in combination
with uranium and/or mixed with radioactive waste. The US Department of Energy Nuclear Criticality
Safety Program (NCSP) has identified calcium as a nuclide needing improvement for supporting criticality
safety analyses. In particular, a consistent set of covariance data is needed in the evaluation to support
sensitivity/uncertainty analyses. As a result, the NCSP initiated new neutron-induced cross section
measurements on calcium to support the development of a new cross-section evaluation in the resonance
region.. The objective of this paper is to present the results of the calcium cross-section measurements
and data analysis. Two types of experiments were performed at the Geel Electron Linear Accelerator
(GELINA) of the Institute for Reference Material and Measurements of the Joint Research Centers, European
Union. A metallic calcium target was placed in Flight Path 14 at a distance of 60 m from the
neutron production target to measure neutron capture with 4 C6D6 detectors. Due to its reactivity with
air, the metallic calcium sample was encapsulated in a thin-wall aluminum container. To correct for the
effect of the aluminum, an empty container of the exact same dimensions was also measured. The same
sample was used in a transmission experiment to determine the total cross section. The sample was placed
in Flight Path 4 at a distance of 50 m from the neutron target. A 1.27-cm thick 6Li glass detector was
used to detect the sample-transmitted neutron. The empty aluminum container served in the open beam
as a compensator for the aluminum in the sample. The final paper will provide the experimental details
and compare the measured cross-section data for calcium with cross sections calculated from the latest
evaluated data files. ORNL is managed by UT-Battelle, LLC, for the U.S. Department of Energy under
Contract No. DE-AC05-00OR22725. The U.S. Department of Energy Nuclear Criticality Safety Program
sponsored the work that is presented in this paper
NA 3 11:20 AM
Measurements of keV-Neutron Capture Cross Sections and Capture Gamma-Ray Spectra
of Pd Isotopes
K. Terada, M. Igashira, T. Katabuchi, T. Matsuhashi, B. Hales
Tokyo Institute of Technology
The nuclear transmutation of long-lived fission products (LLFPs) generated in nuclear fission reactors into
stable or short-lived nuclides by neutron capture reaction is expected to reduce the impact of nuclear waste
disposal on the environment. Palladium-107 (half life: 6.5x10 6 y) is one of the most important LLFPs, and
its neutron capture cross sections are important for the study of LLFP transmutation systems. On the
other hands, the capture cross sections of stable Pd isotopes also affect the performance of a transmutation
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