Voloxidation of Mixed Nitride Uranium-Plutonium Spent Nuclear Fuel

被引：2

作者：

Momotov, V. N. ^{[1
]}

Makarov, A. O. ^{[1
]}

Volkov, A. Yu. ^{[1
]}

Lakeev, P. V. ^{[1
]}

Tikhonova, D. E. ^{[1
]}

Dvoeglazov, K. N. ^{[2
]}

机构：

[1] Res Inst Nucl Reactors, Dimitrovgrad 433510, Ulyanovsk Oblas, Russia

[2] JSC Proryv, Moscow 107140, Russia

来源：

RADIOCHEMISTRY | 2023年 / 65卷 / 02期

关键词：

SNF voloxidation; mixed nitride uranium-plutonium fuel; fission products; radiochemical analysis; tritium; radiocarbon;

D O I：

10.1134/S1066362223020042

中图分类号：

O65 [分析化学];

学科分类号：

070302 ; 081704 ;

摘要：

The efficiency of voloxidation of mixed nitride uranium-plutonium spent nuclear fuel (MNUP SNF) for the separation of the fuel composition from the fuel rod cladding and removal of H-3 and C-14 was estimated. It was shown that the completeness of SNF separation from fuel rod cladding under optimal conditions is at the level of 98-99%. The residual content of tritium in the voloxidized fuel does not exceed 0.2% of its content in the original SNF sample; radiocarbon is removed by 98%.

引用

页码：177 / 184

页数：8

共 32 条

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