Assay of zirconium and americium in the irradiated U-Zr metal alloy fuel slug

被引：1

作者：

Prathibha, T. ^{[1
]}

Suneesh, A. S. ^{[1
]}

Rout, Alok ^{[1
]}

Selvan, Robert ^{[1
]}

Suba, M. Amutha ^{[1
]}

Rao, J. S. Brahmaji ^{[1
]}

Kumar, G. V. S. Ashok ^{[1
]}

Sankar, D. Bola ^{[1
]}

Rajeswari, S. ^{[1
]}

Ramanathan, N. ^{[1
,2
]}

Suresh, A. ^{[1
,2
]}

Jayaraman, V. ^{[1
,2
]}

Sivaraman, N. ^{[1
,2
]}

机构：

[1] Indira Gandhi Ctr Atom Res, Mat Chem & Met Fuel Cycle Grp, Kalpakkam 603102, Tamil Nadu, India

[2] A CI Homi Bhabha Natl Inst, Indira Gandhi Ctr Atom Res, Kalpakkam 603102, Tamil Nadu, India

来源：

JOURNAL OF NUCLEAR MATERIALS | 2024年 / 600卷

关键词：

U-Zr metallic fuel; Irradiation; Liquid-liquid extraction; Spectrophotometry; Alpha spectrometry; Gamma spectrometry; FAST-REACTOR FUEL; FISSION-PRODUCTS; BEHAVIOR; URANIUM; EXTRACTION;

D O I：

10.1016/j.jnucmat.2024.155292

中图分类号：

T [工业技术];

学科分类号：

08 ;

摘要：

An alloy-based fuel comprised of U-Pu-Zr is under development for the futuristic fast reactors to improve fissile atom utilization. As the technical data available with the metal fuel reactors is limited, it is imperative to have an exhaustive comprehension of behavior of fission and activation products before deploying the U-Pu-Zr metal fuel for commercial applications. Towards meeting this objective, the present paper highlights the analytical estimation of Zr and Am in the irradiated U-Zr metal that has experienced a low burn-up. The estimation of Zr was carried out by a modified spectrophotometric method developed in our laboratory. The estimation of Am was accomplished through initial liquid-liquid extraction-based removal of U and Pu by tri-n-butyl phosphate followed by the separation of Am by TODGA from the raffinate. Am was estimated with the help of alpha spectrometry of the Am-separated TODGA phase, and the same has been substantiated by comparing it with the results of gamma spectrometry.

引用

页数：11

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