Neutron Data Measurements for Energy Applications and Nuclear Waste Transmutation at JRC-IRMM

Studies in nuclear energy and transmutation of radioactive waste require neutron data for conceptual and performance studies, to determine the viability of advanced ideas such as an Accelerator Driven System and to fix the safety margins of any new concepts. IRMM's neutron data-measurement program addresses data needs associated with Accelerator Driven Systems, management of radioactive waste, the thorium fuel cycle, safety issues of conventional reactors. Ongoing and recently completed activities include capture and total cross-section measurements for 127,129I, 206Pb, and 232Th; precision total cross-section measurements for 240,242Pu; inelastic-scattering measurements for 52Cr, 58Ni, 209Bi, and 207Pb; (n,2n) measurements for 207Pb, and (n,xp); and (n,x alpha) and (n,xn) cross-section measurements with the activation technique. Capture, total, and inelastic cross-section measurements make use of the pulsed white neutron source Gelina, whereas activation cross sections are determined at the Van de Graaff laboratory. An overview will be given of the above-mentioned activities and an outlook will be provided for the measurements in the near future.

PLOMPEN Arjan; 

2006-11-07

American Institute of Physics

JRC34228

https://publications.jrc.ec.europa.eu/repository/handle/JRC34228,