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Evaluation of Value for Hydrogen Release from High-level Liquid Waste,(IV). Hydrogen Release Rate for .GAMMA.-Ray Radiolysis of Simulated Purex Waste Solutions
高レベル廃液からの放射線分解発生水素量の評価,(IV) 模擬高レベル廃液のγ線分解発生水素量
1997
Journal of the Atomic Energy Society of Japan
高レベル廃液からの放射線分解発生水素量の評価,(IV) 模擬高レベル廃液のγ線分解発生水素量
The rates of hydrogen release from simulated high-level liquid waste (SHLLW) during irradiation of 60Co γ-rays have been studied using a laboratory-scale apparatus. The SHLLW used was made up of 28 different metal elements, the concentrations of which were determined from a computed data (ORIGEN-2) for a Purex spent fuel (burn-up of 4.5GWd/t, cooling time of 4 years) except for those of corrosion products (Fe, Cr and Ni) and of chemical process additive (P). The nitrate ion concentration of the
doi:10.3327/jaesj.39.1062
fatcat:oisrinvjlrb5jhlaphwjzkvzoq