![]() JEFF Scientific Working Group, Joint Evaluated Fission and Fusion File (JEFF) release 3.2. Shibata et al., JENDL-4.0: a new library for nuclear science and engineering. The total kinetic energy release and fission mass distributions for the fast neutron (En 3100 MeV) induced fission of 232Th, 233U, 235U, 237Np, 239Pu. Meet on Neutron Radiation Metrology, Moscow (1983)į. JCGM 100:2008, GUM 1995 with minor corrections Evaluation of Measurement Data-Guide to the Expression of Uncertainty in Measurement. International Organisation for Standardization (ISO). Amouroux, JEFF-Report 24 (Data Bank, Nuclear-Energy Agency, OECD, 2014)Ī.S. JRC Scientific and Technical Reports (2009) Birgersson and Göran Lövestam, NeuSDesc-Neutron Source Description Software Manual. Brown, Monte Carlo Techniques for Nuclear Systems-Theory Lectures. Gressier et al.,, Metrologia 51 (Suppl, Series, 2014), p. Salvatores et al., Report NEA/WPEC-26, Paris (2008) Wang, Evaluation of the neutron data standards. International evaluation of neutron cross section standards. Zhu, ENDF/B-VIII.0: The 8th major release of the nuclear reaction data library with cielo-project cross sections, new standards and thermal scattering data. Žerovnik, The joint evaluated fission and fusion nuclear data library, JEFF-3.3. Netter, Centre dÉtudes Nucleaires Report Series, No. In this paper we introduce a small modular organic liquid scintillator detector array that can detect changes in mass of 238 U between 3.69 g and 14.46 g. Cierjacks, Report: Kernforschungszentrum Karlsruhe Reports No. The ability to detect neutrons from the spontaneous fission of 238 U in samples of depleted uranium with organic liquid scintillation detectors is presented. The results confirm the most recent standard libraries at 2.51 and 14.83 MeV. University of North Texas Libraries, UNT Digital Library, Ĭrediting UNT Libraries Government Documents Department.A measurement campaign to determine neutron induced fission cross sections of \(^\) in parallel. ![]() Some measurements of prompt-neutron fission yield (anti $nu$p) in thermal-neutron fission of $sup 232$U, $sup 238$Pu, $sup 241$Pu, $sup 241$Am, /sup 242m/Am, $sup 243$Cm, $sup 245$Cm, and in spontaneous fission of $sup 244$Cm., ![]() oai/?verb=GetRecord&metadataPrefix=oai_dc&identifier=info:ark/67531/metadc867095 International Image Interoperability Framework (IIIF) Uranium Isotopes U-232/Neutron Fission Of, Prompt Neutron Yield From Thermal, (E).Prompt Neutrons Curium 244- Spontaneous Fission Plutonium Isotopes Pu-241/Neutron Fission Of, Prompt Neutron Yield From Thermal, (E).Plutonium Isotopes Pu-241/Neutron Fission Of, Prompt Neutron Yield From Thermal, (E).Plutonium Isotopes Pu-238/Neutron Fission Of, Prompt Neutron Yield From Thermal, (E).Neutrons, Thermal/Reactions (N,F) With A = 232 To 245 Nuclei, Prompt Neutron Yield From, (E).N36550* -Physics (Nuclear)-Nuclear Properties & Reactions, A >= 90-Nuclear Reactions & Scattering.Curium Isotopes Cm-245/Neutron Fission Of, Prompt Neutron Yield From Thermal, (E).Curium Isotopes Cm-244/Fission Of, Prompt Neutron Yield From Spontaneous, (E).Curium Isotopes Cm-243/Neutron Fission Of, Prompt Neutron Yield From Thermal, (E).Americium Isotopes Am-242/ Neutron Fission Of Isomeric, Prompt Neutron Yield From Thermal, (E).Americium Isotopes Am-241/Neutron Fission Of, Prompt Neutron Yield From Thermal, (E).Americium 241- Americium 242- Curium 243- Curium 245- Fission- Neutron Beams- Plutonium 238- Plutonium 241- Thermal Neutrons- Uranium 232.
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