Survey of Experimentally Determined Neutron Cross Sections of the Actinides

Survey of Experimentally Determined Neutron Cross Sections of the Actinides

Author:

Publisher:

Published: 1973

Total Pages:

ISBN-13:

DOWNLOAD EBOOK

Experimentally determined neutron cross section data for heavy actinides involved in the reactor production chains leading to /sup 238/Pu and /sup 252/Cf were examined. The neutron energy region below one kilovolt is emphasized because these cross sections and reactions are important for thermal and near- thermal reactors. Included with the data summaries are brief descriptions of pertinent measurements in progress or plarmed for the near future at United States and European laboratories. Additional measurements that are needed are suggested. Of most immediate interest are: sigma /sub ny/ for /sup 248/Cm below 1 keV, sigma /sub nf/ for /sup 245/Cm below 40 eV, sigma /sub nf/ for /sup 247/ Cm below 40 eV, and sigma /sub nf/ for /sup 251/Cf below 1 keV. Data were gathered for the survey through January 1973. (auth).


Principle and Uncertainty Quantification of an Experiment Designed to Infer Actinide Neutron Capture Cross-Sections

Principle and Uncertainty Quantification of an Experiment Designed to Infer Actinide Neutron Capture Cross-Sections

Author:

Publisher:

Published: 2010

Total Pages:

ISBN-13:

DOWNLOAD EBOOK

An integral reactor physics experiment devoted to infer higher actinide (Am, Cm, Bk, Cf) neutron cross sections will take place in the US. This report presents the principle of the planned experiment as well as a first exercise aiming at quantifying the uncertainties related to the inferred quantities. It has been funded in part by the DOE Office of Science in the framework of the Recovery Act and has been given the name MANTRA for Measurement of Actinides Neutron TRAnsmutation. The principle is to irradiate different pure actinide samples in a test reactor like INL's Advanced Test Reactor, and, after a given time, determine the amount of the different transmutation products. The precise characterization of the nuclide densities before and after neutron irradiation allows the energy integrated neutron cross-sections to be inferred since the relation between the two are the well-known neutron-induced transmutation equations. This approach has been used in the past and the principal novelty of this experiment is that the atom densities of the different transmutation products will be determined with the Accelerator Mass Spectroscopy (AMS) facility located at ANL. While AMS facilities traditionally have been limited to the assay of low-to-medium atomic mass materials, i.e., A 100, there has been recent progress in extending AMS to heavier isotopes - even to A 200. The detection limit of AMS being orders of magnitude lower than that of standard mass spectroscopy techniques, more transmutation products could be measured and, potentially, more cross-sections could be inferred from the irradiation of a single sample. Furthermore, measurements will be carried out at the INL using more standard methods in order to have another set of totally uncorrelated information.


Nuclear Data for Science and Technology

Nuclear Data for Science and Technology

Author: Syed M. Qaim

Publisher: Springer Science & Business Media

Published: 2012-12-06

Total Pages: 1041

ISBN-13: 3642581137

DOWNLOAD EBOOK

This book describes the Proceedings of the International Conference on Nuclear Data for Science and Technology held at Jillich in May 1991. The conference was in a series of application oriented nuclear data conferences organized in the past under the auspices of the Nuclear Energy Agency-Nuclear Data Committee (NEANDC) and with the support of the Nuclear Energy Agency-Committee on Reactor Physics (NEACRP). It was the fIrst international conference on nuclear data held in Germany, with the scientific responsibility entrusted to the Institute of Nuclear Chemistry of the Research Centre Jillich. The scientific programme was established by the International Programme Committee in consultation with the International Advisers, and the NEA and IAEA cooperated in the organization. A total of 328 persons from 37 countries and fIve international organizations participated. The scope of these Proceedings extends to a wide range of interdisciplinary topics dealing with measu rement, calculation, evaluation and application of nuclear data, with a major emphasis on numerical data. Both energy and non-energy related applications are considered and due attention is given to some fundamental aspects relevant to the understanding of nuclear data.