26.02.2013 Views

Program - Brookhaven National Laboratory

Program - Brookhaven National Laboratory

Program - Brookhaven National Laboratory

SHOW MORE
SHOW LESS

You also want an ePaper? Increase the reach of your titles

YUMPU automatically turns print PDFs into web optimized ePapers that Google loves.

step was to determine which detector and which configuration was better suited to predict fuel burnup and<br />

cooling time. Three different detectors of High Purity Germanium (HPGe), Lanthanum Bromide (LaBr3),<br />

and High Pressure Xenon (HPXe) in two system configurations of above and below the water pool were<br />

used during the study [1]. Data was collected and analyzed in order to create burnup and cooling time<br />

calibration curves for ATR fuel. From spectra taken and the calibration curves obtained, it was determined<br />

that although the HPGe detector yielded better quality spectra alternatives were needed because of the<br />

in-situ nature of the measurements. The ATR fuel scanning system will be located at the canal adjacent to<br />

the reactor and has to be a rugged, low maintenance and an easy to control system. It was concluded that<br />

the LaBr3 and HPXe are better alternatives for canal in-situ measurements and that in order to enhance<br />

the quality of the spectra and burnup predictions obtained with these detectors a deconvolution process<br />

had to developed and applied before the final design of the ATR fuel scanning measurement system was<br />

completed. The deconvolution technique involved determining the response function of the two detectors<br />

using MCNPX. Once the response function of the detectors was determined and validated deconvolution<br />

algorithms were tested to determine which method was better suited for ATR fuel applications. The last<br />

step in the enhancement process will be testing the deconvolution technique against data generated from<br />

models, experimental data from calibration radiation sources and ultimately against high enriched uranium<br />

samples.<br />

[1] J. Navarro, R. Aryaeinejad, D.W. Nigg, A, “Feasibility Study to Determine Cooling Time and Burnup of<br />

Advanced Test Reactor Fuel Using a Nondestructive Technique and Three Types of Gamma-ray Detectors”,<br />

Journal of ASTM International, March 2012, Vol. 9, No. 6, March 2012.<br />

BE 4 11:40 AM<br />

Re-analysis of Fusion Relevant Benchmark Experiments Using Recent Nuclear Data<br />

Libraries<br />

Keitaro Kondo, Ulrich Fischer, Axel Klix, Pavel Pereslavtsev, Arkady Serikov<br />

Karlsruhe Institute of Technology (KIT), Eggenstein-Leopoldshafen, 76344, Germany<br />

With the release of ENDF/B-VII, JENDL-4.0 and JEFF-3.1.2 a set of up-to-date nuclear data libraries<br />

has been made available which are also suitable for fusion technology applications. These data libraries<br />

complement the Fusion Evaluated Nuclear Data Library (FENDL) which is developed under the auspices<br />

of the IAEA/NDS to provide a qualified data library for fusion applications. The version FENDL-2.1,<br />

assembled in 2003, currently serves as the reference data library for ITER nuclear design analyses. A<br />

major update of this library has been provided with the FENDL-3 project of the IAEA, resulting in the<br />

recent starter library FENDL-3/SLIB, release 4. In this work, we re-analyse a wide range of fusion relevant<br />

benchmark experiments conducted previously with 14 MeV neutron generators at Frascati, ENEA (FNG),<br />

the Technical University Dresden (TUD) and the Fusion Neutron Source (FNS) at Tokai-mura, Japan.<br />

Our special focus is on two breeding blankets experiments, which have been performed previously in the<br />

frame of the European fusion programme on two mock-ups of the European Helium-Cooled-Lithium to<br />

Lead (HCLL) and Helium-Cooled-Pebble-Bed (HCPB) test blanket modules (TBMs) for ITER. Tritium<br />

production rates as well as the neutron and photon spectra measured in these mock-ups are compared<br />

with calculations using the FENDL-3/SLIB, release 4 and state-of-the-art nuclear data evaluations, JEFF-<br />

3.1.2, JENDL-4.0 and ENDF/B-VII. Because nuclear data for lead and beryllium have a large impact<br />

on the calculation for these mock-up experiments, several clean benchmark experiments relevant to the<br />

experiments are also analysed. The paper describes detailed results of the analyses performed on the<br />

benchmark experiments. The comparison includes results obtained previously with the FENDL-2.1 data<br />

library and concludes with recommendations on the use of the data libraries for fusion applications.<br />

36

Hooray! Your file is uploaded and ready to be published.

Saved successfully!

Ooh no, something went wrong!