Measurement of Cross Section for the <SUP>103</SUP>Rh(n, n')<SUP>103m</SUP>Rh Reaction and Its Application to Fast Neutron Flux Measurements
スポンサーリンク
概要
- 論文の詳細を見る
Making use of monoenergetic neutrons produced by a 2 MeV Van de Graaff accelerator, the cross section for the <SUP>103</SUP>Rh(n, n')<SUP>103m</SUP>Rh reaction was measured in the energy range from 180 keV to 4.6 MeV. To obtain the relative activity of <SUP></SUP>Rh, the 2103m0keV X-rays emitted by the nuclide were measured with a thin NaI(Tl) scintillator with Be window. For absolute measurement, a standard <SUP>103</SUP>Ru source was made from ruthenium trichloride irradiated with thermal neutrons. The self-shielding effect to the 20 keV X-rays was eliminated by the realization of a thin layer of Ru obtained by electrodeposition.<BR>The fission-spectrum-averaged cross section for this reaction determined by the present method is 558±32 mb, and the effective cross section 960±55mb.<BR>The reaction was applied to the measurement of the fast neutron flux in the experimental facilities of the Kyoto University Reactor. The present report also gives a discussion on the ad-vantage of using the <SUP>103</SUP>Rh(n, n')<SUP>103m</SUP>Rh reaction as fast neutron radiation damage monitor.
著者
-
Kobayashi Katsuhei
Research Reactor Institute Kyoto Uninversity
-
Kimura Itsuro
Research Reactor Institute Kyoto University
-
Shibata Toshikazu
Research Reactor Institute Kyoto University
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
- Absorption and Emission of 2,3-Dimethyl-Naphthalene in n-Hexane Rigid Matrix at 77°K
- Excimer (Excited Dimer) Fluorescence of Naphthalene at 77°K in Rigid Media
- Color Centers in MgO:Ni Induced by Neutron Irradiation
- 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