Benchmark Critical Experiments of a Heterogeneous System of Uranium Fuel Rods and Uranium Solution Poisoned with Gadolinium, and Application of Their Results to JACS Validation
スポンサーリンク
概要
- 論文の詳細を見る
A series of critical experiments were performed using heterogeneous cores at the Static Experiment Critical Facility (STACY) of the Japan Atomic Energy Agency (JAEA) in order to obtain systematic benchmark criticality data concerning the dissolving process in reprocessing plants. Focusing on the use of gadolinium as a soluble poison, critical mass was measured for a combination of uranium dioxide fuel rods (5 wt% 235U) and uranyl nitrate solution (6 wt% 235U) poisoned with gadolinium (Gd). Fuel rods were arrayed with a 1.5 cm lattice interval in the poisoned fuel solution in a 60-cm-diameter cylindrical tank. The uranium concentration of the solution was roughly kept at about 330 gU/L, and the Gd concentrations were varied up to 0.1 gGd/L. The other series of experiments were also conducted, as reference cases, varying uranium concentration in the fuel solution without Gd. The results provided benchmark criticality data for validation of neutron multiplication factor calculation on heterogeneous systems such as a dissolver. Validation calculation of JACS based on the newly obtained benchmarks supports the justification of its utilization for the criticality safety analysis.
- 2011-07-01
著者
-
MIYOSHI Yoshinori
Nuclear Safety Research Center, Japan Atomic Energy Agency
-
Uchiyama Gunzo
Nuclear Safety Research Center Japan Atomic Energy Agency
-
Tonoike K
Nuclear Safety Research Center Japan Atomic Energy Agency
-
Tonoike Kotaro
Nuclear Safety Research Center Japan Atomic Energy Agency
-
Miyoshi Yoshinori
Nuclear Safety Research Center Japan Atomic Energy Agency
関連論文
- Benchmark Critical Experiments and FP Worth Evaluation for a Heterogeneous System of Uranium Fuel Rods and Uranium Solution Poisoned with Pseudo-Fission-Product Elements
- Nuclear Criticality Safety Evaluation of a Mixture of MOX, UO_2 and Additive in the Most Conservative Concentration Distribution
- Measurement of Neutron Dose under Criticality Accident Conditions at TRACY Using TLDs
- Effect of Higher-Harmonic Flux in Exponential Experiment for Subcriticality Measurement
- Real Time α Value Measurement with Feynman-α Method Utilizing Time Series Data Acquisition on Low Enriched Uranium System
- Kinetic Parameter β_/l Measurement on Low Enriched Uranyl Nitrate Solution with Single Unit Cores (600φ, 280T,800φ) of STACY
- Benchmark Critical Experiments of a Heterogeneous System of Uranium Fuel Rods and Uranium Solution Poisoned with Gadolinium, and Application of Their Results to JACS Validation
- Criticality Safety Benchmark Experiment on 10% Enriched Uranyl Nitrate Solution Using a 28-cm-Thickness Slab Core
- Benchmark Critical Experiments of a Heterogeneous System of Uranium Fuel Rods and Uranium Solution Poisoned with Gadolinium, and Application of Their Results to JACS Validation
- Fluctuation of the Neutron Multiplication Factor Induced by an Oscillation of the Fuel Solution System
- Effect of Higher-Harmonic Flux in Exponential Experiment for Subcriticality Measurement