Computation on Fuel Particle Size Capable of Being Regarded as Homogeneous in Nuclear Criticality Safety Analysis.
スポンサーリンク
概要
- 論文の詳細を見る
For powdered fuel processed in the nuclear fuel facilities, flooding is often thought to be the severest condition regarding the nuclear criticality safety evaluation. The reactivity of such a heterogeneous system as powdered fuel in water should be almost equal to that of the homogeneous one, when the fuel particle size is very small. The neutron multiplication factor was calculated for an infinite cubic array of slightly enriched UO<SUB>2</SUB> sphere particles immersed in water with various enrichments, water to fuel ratios and fuel particle sizes. The calculations were performed with a computer code module based on the collision probability method to solve the ultra-fine energy group equations of neutrons. The change in the neutron multiplication factor from the homogeneous system is dominated first by the change in the resonance escape probability and second by the change in the thermal utilization factor ; these changes and therefore their sum, depend almost completely on the mean uranium concentration (or water to fuel volume ratio) and rarely on uranium enrichment up to 10 wt% for a fuel particle size of 1 mm. The dependence determines the fuel particle size regarded as homogeneous in proportion to the negligible relative error of the neutron multiplication factors.
- 一般社団法人 日本原子力学会の論文
著者
-
OKUNO Hiroshi
Japan Atomic Energy Agency
-
NAITO Yoshitaka
Japan Atomic Energy Research Institute
-
OKUDA Yasuhisa
Sumitomo Atomic Energy Industries, Ltd.
関連論文
- Nuclear Criticality Safety Evaluation of a Mixture of MOX, UO_2 and Additive in the Most Conservative Concentration Distribution
- Calculation of Critical Concentrations of Actinides in an Infinite Medium of Silicon Dioxide
- Critical and Subcritical Mass Calculations of Curium-243 to -247 Based on JENDL-3.2 for Revision of ANSI/ANS-8.15
- A Method to Calculate Sensitivity Coefficients of Reactivity to Errors in Estimating Amounts of Nuclides Found in Irradiated Fuel
- Calculation of Nuclear Characteristic Parameters and Drawing Subcriticality Judgment Graphs of Infinite Fuel Systems for Typical Nuclear Fuels
- Calculation of Criticality Condition Data for Single-unit Homogeneous Uranium Materials in Six Chemical Forms
- Deuterium Effect on the Subcritical Limit for Fissile-to-Hydrogen Ratio
- Effects of Organic Solvent on Infinite Neutron Multiplication Factor of Homogeneous Plutonium Nitrate Solution System
- Development of a Statistical Method for Evaluation of Estimated Criticality Lower-Limit Multiplication Factor Depending on Uranium Enrichment and H/Uranium-235 Atomic Ratio
- Classification of Criticality Calculations with Correlation Coefficient Method and Its Application to OECD/NEA Burnup Credit Benchmarks Phase III-A and II-A
- Classification of Criticality Calculations with Correlation Coefficient Method and Its Application to OECD/NEA Burnup Credit Benchmarks Phase III-A and II-A
- Computation on Fuel Particle Size Capable of Being Regarded as Homogeneous in Nuclear Criticality Safety Analysis.
- Moderator temperature coefficient in BWR core.
- A new mixed method with finite difference and finite element method for neutron diffusion calculation.