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          Minor Actinide Neutron Reaction Data (MANREAD)

          Closed for Proposals

          Project Type

          Coordinated Research Project

          Project Code

          F41024

          CRP

          1409

          Approved Date

          20 December 2006

          Project Status

          Closed

          Start Date

          1 July 2007

          Expected End Date

          30 June 2011

          Completed Date

          27 July 2012

          Description

          The strategies foreseen for future development and employment of nuclear power generation underline the use of nuclear energy systems in which the nuclear fuel contains consistent and controlled amounts of the minor actinides (MA). These minor actinides, particularly neptunium and americium, are produced as normal by-products of the operation of thermal power reactors. Because of the existence of long-lived isotopes of these elements, they constitute the major sources of the radiation in spent fuel and in wastes resulting from their reprocessing. Reliable and accurate neutron-induced reaction cross section data are required for the important isotopes of these MAs, including reasonably low uncertainties for sound core design studies and high burn-up strategies.

          The Agency has initiated a Coordinated Research Project on “Neutron Reaction Data for Minor Actinides (MANREAD)” as part of a worldwide effort to determine the present status of our knowledge on MA neutron reaction data. Experimental facilities will be assessed to undertake measurements of neutron reaction cross sections for the important isotopes of the MA elements. The CRP is expected to deliver the results of this experimental, theoretical and nuclear data evaluation work by the end of 2011

          Objectives

          The overall objectives of the CRP are the critical evaluation, uncertainty assessment and production of neutron cross section data for an agreed set of minor actinides. This CRP is composed of research groups performing relevant experiments at the most appropriate facilities in Europe, United States of America, Japan and elsewhere, addressing agreed overall objectives of the CRP and delivering up-to-date results on neutron reaction data for the minor actinides.

          Specific Objectives

          A worldwide assessment will be made of the experimental capabilities to undertake measurements of neutron reaction cross sections for the important isotopes of the minor actinides;

          Publish a final technical report and make new reaction cross section data available online and for distribution on CD-ROM.

          Report measurements of neutron-induced reaction cross sections on MA just completed or planned in the period of activity of the CRP, at research laboratories worldwide;

          Uncertainty assessment of available experimental information on MA neutron cross section data (including data from measurements to be performed in the next two-year period). Assessment of the quality and uncertainties of MA data present in the evaluated nuclear data libraries (ENDF/B-VII, JEFF3.1, BROND-2.2, JENDL-3.3, etc.);

          Impact

          The CRP participants were able to measure, assess and evaluate neutron induced reaction cross sections for a set of minor actinides ( 234,236U, 237Np, 238,240,241,242Pu, 241,242,242m,243Am). These newly obtained experimental and evaluated data will be incorporated in the next releases of national data libraries such as ENDF/B, JEFF, JENDL, CENDL and BROND, and will provide more accurate inputs for reactor core designing. In such a way the results of this CRP will have a significant impact on developments of next generation nuclear energy systems (e.g., GEN IV reactors, accelerator-driven minor actinide burner, hybrid fusion-fission system) carried out by Member States.

          Relevance

          237Np(n,f) cross sections measured at LANL LANSCE facility was used as an input to the least-squares analysis (GMA) for evaluation of JENDL-4.0.

          CRP Publications

          RUS/State Scientific Center of the Russian Federation
          Journal article
          2011
          Neutron fission cross sections and resonance integrals for Cm-246-248 (Atom. Energy 109, 408)
          USA/Group LANSCE-NNS
          Journal article
          2007
          Measurement of the 237Np(n,?) cross section from 20 meV to 500 keV with a high efficiency, highly segmented 4p BaF2 detector (Phys. Rev. C 75, 034610)
          USA/Group LANSCE-NNS
          Journal article
          2008
          Neutron capture cross section of 241Am (Phys.Rev.C78, 034609)
          RUS/State Scientific Center of the Russian Federation
          Journal article
          2012
          243-Am neutron fission cross section and resonance parameters (Atom. Energy 111, 428)
          USA/Group LANSCE-NNS
          Journal article
          2010
          Cross Sections for 239Pu(n,f) and 241Pu(n,f) in the Range En= 0.01 eV to 200 MeV (Nucl. Sci. Eng. 165, 224)
          ITA/Istituto Nazionale di Fisica Nucleare; FRA/Commissariat à l'énergie atomique (CEA); BEL/Institute for Reference Materials and Measurements (IRMM); USA/Group LANSCE-NNS; GFR/Forschungszentrum Karlsruhe GmbH (FZK); AUS/Vienna Environmental Research Accelerator; GRE/National Technical University of Athens
          Journal article
          2010
          Neutron-induced fission cross section of 234U and 237Np measured at the CERN Neutron Time-of-Flight (n_TOF) facility, Phys. Rev. C82, 034601.
          RUS/State Scientific Center of the Russian Federation
          Journal article
          2009
          Cm-243 neutron fission cross section (Atom. Energy, 107, 110)
          BEL/Institute for Reference Materials and Measurements (IRMM)
          Journal article
          2007
          High Resolution Measurement of the 234U(n,f) Cross Section in the Neutron Energy Range from 0.5 eV to 100 keV (Nucl. Sci. Eng. 156, 211)
          RUS/State Scientific Center of the Russian Federation
          Journal article
          2010
          Cm-244 subbarrier fission cross-section (Phys.Atom.Nucl.73, 1487)
          USA/Group LANSCE-NNS
          Journal article
          2009
          Neutron induced fission of 240,242Pu from 1 eV to 200 MeV (Phys.Rev.C79, 014613)
          USA/Group LANSCE-NNS
          Journal article
          2008
          Subthreshold Fission Cross Section of 237Np (Nucl. Sci. Eng. 159, 94)
          FRA/Commissariat à l'énergie atomique (CEA)
          Journal article
          2010
          Neutron-induced fission cross sections of short-lived actinides with the surrogate reaction method (Phys.Lett.B692, 297)
          BEL/Institute for Reference Materials and Measurements (IRMM); USA/Group LANSCE-NNS; GFR/Forschungszentrum Karlsruhe GmbH (FZK);
          Journal article
          2010
          High resolution measurements of the 241Am(n,2n) reaction cross section (Phys.Rev.C81, 064604)
          ITA/Istituto Nazionale di Fisica Nucleare; FRA/Commissariat à l'énergie atomique (CEA); BEL/Institute for Reference Materials and Measurements (IRMM); USA/Group LANSCE-NNS; GFR/Forschungszentrum Karlsruhe GmbH (FZK); AUS/Vienna Environmental Research Accelerator; GRE/National Technical University of Athens
          Journal article
          2011
          Measurement of the 236U(n,f) cross section from 170 meV to 2 MeV at the CERN n_TOF facility (Phys.Rev. C84, 044618)
          RUS/State Scientific Center of the Russian Federation
          Journal article
          2009
          Am-242m and Cm-245 neutron fission cross sections (Atom. Energy 106, 133)
          JPN/Japan Atomic Energy Agency (JAEA)
          Journal article
          2009
          JENDL Actinoid File 2008 (J. Nucl. Sci. Technol. 46, 510)
          JPN/Japan Atomic Energy Agency (JAEA)
          Journal article
          2011
          JENDL-4.0: A new library for nuclear science and engineering (J. Nucl. Sci. Technol. 48, 1)
          USA/Group LANSCE-NNS
          Journal article
          2007
          Neutron induced fission cross section of 237Np from 100 keV to 200 MeV (Phys.Rev.C75, 034610)

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