Determining the swelling of mixed nitride uranium-plutonium fuel based on the post-reactor studies of experimental BN-600 and BOR-60 fuel rods

被引：0

作者：

Zabudko, L. M. ^{[1
]}

Grachev, A. F. ^{[1
]}

Porollo, S. I. ^{[2
]}

Marinenko, E. E. ^{[2
]}

Kryukov, F. N. ^{[3
]}

Beljaeva, A. V. ^{[3
]}

Skupov, M. V. ^{[4
]}

Tarasov, B. A. ^{[4
]}

机构：

[1] JSC Proryv, Moscow, Russia

[2] JSC SSCRF IPPE, Obninsk, Russia

[3] JSC SSC RIIAR, Dimitrovgrad, Russia

[4] JSC VNIINM, Moscow, Russia

来源：

ATOMIC ENERGY | 2023年 / 134卷 / 1-2期

关键词：

621.039.531;

D O I：

10.1007/s10512-023-01024-0

中图分类号：

TL [原子能技术]; O571 [原子核物理学];

学科分类号：

0827 ; 082701 ;

摘要：

A total number of 18 experimental fuel assemblies (FAs), containing mixed nitride fuel rods with claddings of various geometry, were irradiated in an BN-600 core. By the end of 2022, JSC SSC NIIAR had completed the post-reactor studies of 16 ETVS BN-600 nitride fuel rods, 4 fuel rods with a gas sublayer irradiated in the composition of OU-1 and OU- 2 collapsible irradiation devices, and 3 OU-4 BOR-60 fuel rods with a liquid metal sublayer. Post-reactor studies of nitride fuel rods were preceded by pre- test calculations of their stress-strain and temperature states, taking into account the actual irradiation parameters. The results of the studies were compared with the calculated data. Fuel radiation swelling represents one of the most important factors that determine the degree of thermomechanical interaction between the fuel and the cladding, thus limiting the performance of nitride fuel rods. The present article summarizes and analyzes the currently obtained data on the swelling and its rate for mixed uranium-plutonium nitride fuel in fuel rods with a gas sublayer.

引用

页码：39 / 45

页数：7