Measurement and covariance analysis of californium-252 spectrum averaged cross sections.
スポンサーリンク
概要
- 論文の詳細を見る
The <SUP>252</SUP>Cf fission spectrum averaged cross sections for twelve reactions have been measured relative to the cross section for the <SUP>27</SUP>Al (n, α)<SUP>24</SUP>Na reaction. The uncertainties of the measurements are analyzed with regard to the covariances of experimental data.It is demonstrated how to generate and combine the experimental uncertainties in the form of a variance-covariance matrix. The result of the uncertainty analysis taking account of correlations between the experimental data is given. A non-diagonal weighted least square fit has been applied to normalize the measured ratios. Comparing with the standard deviation processed previously using variances only, the standard deviation obtained by the present analysis has been reduced to almost half. This may be due to the developed and improved error analysis based on the covariances between measured data. The meas-ured values of the average cross sections presented here are compared with the calculated ones based on the energy dependent cross sections.
- 一般社団法人 日本原子力学会の論文
著者
-
Kobayashi Katsuhei
Research Reactor Institute Kyoto Uninversity
-
Kimura Itsuro
Research Reactor Institute Kyoto University
-
MANNHART Wolf
Physikalisch-Technische Bundesanstalt
関連論文
- Measurement of Neutron Capture Cross Section of ^Np from 0.02 to 100eV
- Enhanced Diffusion and Lattice Location of Indium and Gallium Implanted in Silicon
- Measurements of Neutron-induced Fission Cross Section of Protactinium-231 from 0. 1eV to 10keV with Lead Slowing-down Spectrometer and at 0. 0253eV with Thermal Neutron Facility
- Measurements of Neutron-induced Fission Cross Section of Americium-243 from Thermal Neutron Energy to 15keV Using Lead Slowing-down Spectrometer and Thermal Neutron Facility
- Neutron Capture Cross Section Measurement of Praseodymium in the Energy Region from 0.003eV to 140keV
- Measurement of Neutron Capture Cross Section of ^Np by Linac Time-of-Flight Method and with Linac-driven Lead Slowing-down Spectrometer
- Application of BGO Scintillators to Absolute Measurement of Neutron Capture Cross Sections between 0. 01 eV and 10 eV
- Behavior of Excess Te Atoms in Undoped p-type CdTe Annealed under Te Vapor Pressures
- Anodic Oxidation of CdTe as a Thin-Layer Removal Technique
- Production of Pure ^Pu Tracer for the Assessment of Plutonium in the Environment
- Ion-Implanted Arsenic Profiles in GaAs Encapsulated by SiO_2 and Si_3N_4
- Comparison between Concentration Profiles of Arsenic Implanted in Silicon Measured by Means of Neutron Activation Analysis and Radioactive Ion Implantation
- Concentration Profiles of Room Temperature Ion Implanted Indium in Silicon
- Enhanced Diffusion of Ion Implanted Sb in Silicon
- Halogen and Mercury Lamp Annealing of Arsenic Implanted into Silicon
- Radioactive Analysis of Palladium Used for an Explosive Cold Fusion Experiment
- Determination of Thermal and Intermediate Neutron Spectrum at UTR-KINKI Using Cd-Ratio Measurements by Activation Method
- Annealing Behavior of Arsenic and Gallium Implanted in Silicon with Thin Native-Oxide Films
- Effects of Neutron Resonance Interference between Ta and Au
- Flux Distribution in Phantom for Biomedical Use of Beam-Type Thermal Neutrons
- Neutron Capture Cross Section Measurement of Praseodymium in the Energy Region from 0.003eV to 140keV
- Measurement and analysis of neutron spectra in lithium fluoride and polytetrafluoroethylene piles.
- Cross section measurement for 199Hg(n,n')199mHg reaction from 0.78 to 6.3MeV.
- Measurement and analysis of fast neutron spectra in iron, nickel and chromium.
- Measurement of neutron capture cross sections with Fe-filtered beam.
- Precision Neutron Total Cross Section Measurements Near 24 keV
- Measurement of Cross Section for the 103Rh(n, n')103mRh Reaction and Its Application to Fast Neutron Flux Measurements
- Measurement of Fission Cross Section of Neptunium-237 in Resonance Region with Electron Linac-Driven Lead Spectrometer.
- Assessment of neutron cross sections for titanium with neutron spectrum in titanium pile.
- Neutron capture cross section measurements of Nb-93, I-127, Ho-165, Ta-181 and U-238 between 3.2 and 80keV.
- Fission spectrum averaged cross sections of some threshold reactions measured with fast reactor "YAYOI".
- Measurement and analysis of neutron spectrum in spherical pile of thoria.
- Measurement and analysis of neutron spectrum in a molybdenum pile.
- Some relations of neutronic noise with fluctuation of inlet coolant temperature and vibration of a control rod obtained by simultaneous measurements at KUR.
- Neutron spectrum in small iron pile surrounded by lead reflector.
- Measurement and covariance analysis of californium-252 spectrum averaged cross sections.
- Measurement of neutron capture cross section of thorium-232 from 1 keV to 408 keV.
- Measurement of neutron total cross section of silicon at 146- and 53.5-keV windows.
- Preparation of Uranium-233 with Low Uranium-232 Content