Promising Fuel Materials for Thermionic Nuclear Power Installations

被引：3

作者：

Alekseev, S. V. ^{[1
]}

Vybyvanets, V. I. ^{[1
]}

Gontar', A. S. ^{[1
]}

Lyubimov, D. Yu. ^{[1
]}

Nelidov, M. V. ^{[1
]}

机构：

[1] Res Inst & Sci Ind Assoc Luch NII NPO Luch, Podolsk, Moscow Oblast, Russia

来源：

ATOMIC ENERGY | 2014年 / 115卷 / 06期

关键词：

FISSION-PRODUCTS; CHEMICAL-STATE;

D O I：

10.1007/s10512-014-9801-8

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：

The properties of the high-temperature monocompounds of uranium UO2, UN, UC, US, and UP are analyzed for the operating conditions of the fuel elements in thermionic nuclear power installations. The advantages and disadvantages of each of these fuels, whose properties do not meet entirely the specifications for long-life thermionic fuel elements, are shown. The results obtained at NII NPO Luch on the basis of these monocompounds of uranium are presented: sub-stoichiometric uranium dioxide with thermally stabilized, predominantly open porosity and with columnar optimized grain structure as well as high-thermalconductivity fuel compositions - solid solutions based on uranium carbide UC-TaC(ZrC), uraniumzirconium carbonitride and uranium carbosulfide. The uses best suited for each of these fuels are determined. A promising design for fuel elements with a multirod kernel, making it possible to solve the problem of removing gaseous fission products from the fuel-element cavity and securing the geometric stability of cladding, is presented for the fuel compositions UC-TaC(ZrC), whose exhibit the lowest evaporation rate.

引用

页码：391 / 401

页数：11

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