Re-evaluation of the thermal neutron capture cross section of 147Nd

Abstract In this paper we are proposing a re-evaluation of the thermal-neutron induced capture cross section of 147Nd. A unique measurement exists from which this cross section was calculated in 1974. This original calculation is based on an assumed value for a specific gamma-ray fraction (called F2), taken from the neighboring nucleus 145Nd. With the availability of reaction codes such as TALYS, such fraction can nowadays be calculated using specific reaction models and parameters. The new value of F2 indicates a decrease of the thermal cross section by 45%, leading to 243 barns, instead of the 440 barns previously reported. This new cross section impacts the calculation of the number density for the well-known burn-up indicator 148Nd, but as shown, the change is close to the usual experimental uncertainties for the 148Nd number densities, thus having a limited impact on burn-up calculation.

[1]  E. Bauge,et al.  Lane consistent, semimicroscopic nucleon nucleus optical model , 2001 .

[2]  Arjan J. Koning,et al.  Local and global nucleon optical models from 1 keV to 200 MeV , 2003 .

[3]  J. Potters,et al.  A study of gamma-ray spectra of thermal neutron capture in 143Nd and 145Nd; Including directional anisotropy and linear polarization measurements of such gamma rays from aligned 143Nd nuclei , 1968 .

[4]  Petter Helgesson,et al.  Efficient Use of Monte Carlo: Uncertainty Propagation , 2014 .

[5]  G. G. Stokes.  "J." , 1890, The New Yale Book of Quotations.

[6]  K. Suyama,et al.  Effect of Neutron Induced Reactions of Neodymium-147 and 148 on Burnup Evaluation , 2005 .

[7]  N. M. Larson,et al.  ENDF/B-VII.1 Nuclear Data for Science and Technology: Cross Sections, Covariances, Fission Product Yields and Decay Data , 2011 .

[8]  Arjan J. Koning,et al.  Modern Nuclear Data Evaluation with the TALYS Code System , 2012 .

[9]  Said F. Mughabghab,et al.  Atlas of neutron resonances , 2018 .

[10]  K. Shibata,et al.  JENDL-4.0: A New Library for Nuclear Science and Engineering , 2011 .

[11]  Manuel Bossant,et al.  JANIS 4: An Improved Version of the NEA Java-based Nuclear Data Information System , 2014 .

[12]  Arjan J. Koning,et al.  Towards sustainable nuclear energy: Putting nuclear physics to work , 2008 .

[13]  S. Kailas,et al.  RIPL – Reference Input Parameter Library for Calculation of Nuclear Reactions and Nuclear Data Evaluations , 2009 .

[14]  B. Pritychenko,et al.  Towards a More Complete and Accurate Experimental Nuclear Reaction Data Library (EXFOR): International Collaboration Between Nuclear Reaction Data Centres (NRDC) , 2014, 2002.07114.

[15]  L. M. Petrie,et al.  Revised uranium--plutonium cycle PWR and BWR models for the ORIGEN computer code , 1978 .

[16]  Uhl,et al.  Test of gamma-ray strength functions in nuclear reaction model calculations. , 1990, Physical review. C, Nuclear physics.