Tests of fuel elements with uranium-plutonium nitride fuel in an IGR pulsed reactor

被引：0

作者：

A. V. Kaplienko

V. V. Lemekhov

Yu. S. Cherepnin

A. V. Moiseyev

A. P. Zhirnov

A. N. Ivanyuta

I. M. Rozhdestvenskiy

D. Yu. Loginov

Ye. R. Mezhina

A. L. Izhutov

Ye. A. Zvir

G. V. Shevlyakov

I. N. Volkova

Ye. G. Batyrbekov

V. V. Baklanov

A. G. Korovikov

A. N. Kotlyar

A. A. Miller

R. A. Irkimbekov

A. D. Vurim

机构：

[1] JSC NIKIET,

[2] JSC “RIAR”,undefined

[3] RSE NNC RK,undefined

来源：

Atomic Energy | 2023年 / 134卷

关键词：

621.039.553;

D O I：

暂无

中图分类号：

学科分类号：

摘要：

Fuel elements with mixed uranium-plutonium nitride fuel were tested in an IGR reactor to justify their application in a BREST-OD-300 reactor. The mid-radial enthalpy limit for the fresh mixed nitride fuel as experimentally determined during IGR launching with fast reactivity input amounted to 167 cal/g. The maximum temperature of 1000 °C and its maintenance for 100 s, comprising one of the design limits for the fuel cladding temperature, was experimentally confirmed. The main results of the performed experiments and post-irradiation studies are analyzed.

引用

页码：275 / 282

页数：7

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[1] Tests of fuel elements with uranium-plutonium nitride fuel in an IGR pulsed reactor
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