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Neutron cross section

  • Neutron-Induced Fission Cross Section of 240,242Pu up to En = 3 Mev

    Neutron-Induced Fission Cross Section of 240,242Pu up to En = 3 Mev

  • Neutron Capture Cross Sections of Cadmium Isotopes

    Neutron Capture Cross Sections of Cadmium Isotopes

  • EVALUATION of NEUTRON CROSS SECTIONS for Cm-242, -243, -244

    EVALUATION of NEUTRON CROSS SECTIONS for Cm-242, -243, -244

  • Testing of Evaluated Transactinium Isotope Neutron Data and Remaining Data Requirements

    Testing of Evaluated Transactinium Isotope Neutron Data and Remaining Data Requirements

  • AN34 Application Note Experiment 17 Neutron Activation Analysis

    AN34 Application Note Experiment 17 Neutron Activation Analysis

  • Neutron Cross Section Evaluation of U-238

    Neutron Cross Section Evaluation of U-238

  • Lecture 5 — Wave and Particle Beams

    Lecture 5 — Wave and Particle Beams

  • Moderator Design for Accelerator Based Neutron Radiography and Tomography Systems

    Moderator Design for Accelerator Based Neutron Radiography and Tomography Systems

  • 3.22 Measurement of Neutron Spallation Cross Sections

    3.22 Measurement of Neutron Spallation Cross Sections

  • Fast Neutron Cross Sections of 2L*°Pu; Measured Results and a Comparison

    Fast Neutron Cross Sections of 2L*°Pu; Measured Results and a Comparison

  • Nuclear Data Development at the European Spallation Source

    Nuclear Data Development at the European Spallation Source

  • Neutron Total Cross Section Measurements of Gold and Tantalum at the Nelbe Photoneutron Source

    Neutron Total Cross Section Measurements of Gold and Tantalum at the Nelbe Photoneutron Source

  • Optimization of Transcurium Isotope Production in the High Flux Isotope Reactor

    Optimization of Transcurium Isotope Production in the High Flux Isotope Reactor

  • The Neutron Cross Section Standards, Evaluations and Applications

    The Neutron Cross Section Standards, Evaluations and Applications

  • Neutron Scattering

    Neutron Scattering

  • Introduction

    Introduction

  • A Proposal for a New Neutron Moderator Material for Accelerator-Based BNCT

    A Proposal for a New Neutron Moderator Material for Accelerator-Based BNCT

  • Temperature Dependence of Neutron Cross-Sections

    Temperature Dependence of Neutron Cross-Sections

Top View
  • Neutron Activation Analysis with ^-Standardisation : General Formalism and Procedure
  • Neutron Capture Cross Sections of Selenium Isotopes
  • Total Cross-Sections of U, UO2 and Tho2 for Thermal and Subthermal Neutrons
  • Introduction to Neutron Scattering Lecture Notes of the Introductory Course 1St European Conference on Neutron Scattering (ECNS '96)
  • An Introduction to Neutron Scattering
  • Table of Thermal Neutron Cross Sections of the Isotopes
  • Neutron Beams
  • Measuring Spin Waves
  • An Improved Slow Neutron Spectrometer at the Research Reactor-R1
  • Review and Assessment of Neutron Cross Section and Nubar Covariances for Advanced Reactor Systems
  • Neutron Capture Cross Section Measurement of U 238 at the CERN N-TOF Facility in the Energy Region from 1 Ev to 700 Kev
  • Jef-1 Scattering Law Data
  • Neutrons for Scattering: What They Are, Where to Get Them, and How to Deal with Them
  • Special Feature Neutron Scattering Lengths and Cross Sectioirn
  • Neutron Activation Measurements for Materials Used in Fusion Reactors
  • EVALUATED NUCLEAR DATA for NUCLIDES WITHIN the THORIUM–URANIUM FUEL CYCLE the Following States Are Members of the International Atomic Energy Agency
  • Module 3: Neutron Induced Reactions
  • Spin-Echo Small-Angle Neutron Scattering Study of the Domain


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