Development of a Comprehensive Code for Nuclear Data Evaluation, CCONE, and Validation Using Neutron-Induced Cross Sections for Uranium Isotopes
スポンサーリンク
概要
- 論文の詳細を見る
A new comprehensive code for nuclear data evaluation, CCONE, has been developed for the evaluation of nuclear data for actinides. Neutron-induced reaction cross sections for uranium isotopes (A = 232, 233, 234, 235, 236, 237, 238) were analyzed for incident energies from 10 keV to 20 MeV using CCONE in order to validate its capability. Reproducibility of the cross section calculations for various reactions such as total, fission, capture, and (n, 2n) was tested using simple parameterization. The calculated cross sections and neutron emission spectra show good agreement with the experimental data.
- 一般社団法人 日本原子力学会の論文
- 2007-05-25
著者
-
IWAMOTO Osamu
Nuclear Data Center, Japan Atomic Energy Research Institute
-
Iwamoto Osamu
Nuclear Sci. And Engineering Directorate Japan Atomic Energy Agency
関連論文
- Application of Tail Subtraction Technique with Particle Identification to a Stacked Spectrometer for Intermediate Energy Protons
- Systematics of Prompt Fission Neutron Spectra
- Development of a Comprehensive Code for Nuclear Data Evaluation, CCONE, and Validation Using Neutron-Induced Cross Sections for Uranium Isotopes
- Production of an Isomeric State of 90Y by Fast Neutrons for Nuclear Diagnostics
- Radioactive Tracer 132Cs (TRACs) for Fukushima Nuclear Power Plant Accident
- New Production Routes for Medical Isotopes
- Generation of Radioisotopes with Accelerator Neutrons by Deuterons
- Generation of Radioisotopes with Accelerator Neutrons by Deuterons
- New Production Routes for Medical Isotopes ⁶⁴Cu and ⁶⁷Cu Using Accelerator Neutrons