Search SciRate

1 results for au:Cude_Woods_C in:cond-mat

Show all abstracts

The Upscattering of Ultracold Neutrons from the polymer $[C_6 H_{12}]_n$
E. I. Sharapov, C. L. Morris, M. Makela, A. Saunders, Evan R. Adamek, L. J. Broussard, C. B. Cude-Woods, Deion E Fellers, Peter Geltenbort, M. Hartl, S. I. Hasan, K. P. Hickerson, G. Hogan, A. T. Holley, C. M. Lavelle, Chen-Yu Liu, M. P. Mendenhall, J. Ortiz, R. W. Pattie Jr., J. Ramsey, et al (11)
Aug 14 2013 cond-mat.mtrl-sci nucl-ex arXiv:1308.2710v1

@misc{1308.2710, author = {E.~I.~Sharapov and C.~L.~Morris and M.~Makela and A.~Saunders and Evan R.~Adamek and L.~J.~Broussard and C.~B.~Cude-Woods and Deion E Fellers and Peter Geltenbort and M.~Hartl and S.~I.~Hasan and K.~P.~Hickerson and G.~Hogan and A.~T.~Holley and C.~M.~Lavelle and Chen-Yu Liu and M.~P.~Mendenhall and J.~Ortiz and R.~W.~Pattie Jr.~and J.~Ramsey and D.~J.~Salvat and S.~J.~Seestrom and E.~Shaw and Sky Sjue and W.~E.~Sondheim and B.~VornDick and Z.~Wang and T.~L.~Womack and A.~R.~Young and Bryan A.~Zeck and D.~G.~Phillips}, title = {{T}he {U}pscattering of {U}ltracold {N}eutrons from the polymer $[{C}_6 {H}_{12}]_n$}, year = {2013}, eprint = {1308.2710}, howpublished = {Phys. Rev. C 88, 064605 (2013)}, doi = {10.1103/PhysRevC.88.064605}, note = {arXiv:1308.2710v1} }
PDF
It is generally accepted that the main cause of ultracold neutron (UCN) losses in storage traps is the upscattering to the thermal energy range by hydrogen adsorbed on the surface of the trap walls. However, the data on which this conclusion is based are poor and contradictory. Here, we report a measurement, performed at the Los Alamos National Laboratory UCN source, of the average energy of the flux of upscattered neutrons after the interaction of UCN with hydrogen bound in semicrystalline polymer PMP (tradename TPX), [C$_{6}$H$_{12}$]$_n$. Our analysis, performed with the MCNP code based on the application of the neutron scattering law to UCN upscattered by bound hydrogen in semicrystalline polyethylene, [C$_{2}$H$_{4}$]$_n$, leads us to a flux average energy value of 26$\pm3$ meV in contradiction with previously reported experimental values of 10 to 13 meV and in agreement with the theoretical models of neutron heating implemented in the MCNP code.