Molten salt fast reactor with U-Pu fuel cycle

被引：14

作者：

Degtyarev, Alexej ^{[1
]}

Myasnikov, Andrej ^{[1
]}

Ponomarev, Leonid ^{[2
]}

机构：

[1] Natl Res Ctr Kurchatov Inst, Moscow, Russia

[2] Russian Acad Sci, Moscow, Russia

来源：

PROGRESS IN NUCLEAR ENERGY | 2015年 / 82卷

关键词：

Liquid nuclear fuel; Fast reactor; Molten salt reactor; Solubility of the minor actinides; Subcritical reactor-burner; SOLUBILITY;

D O I：

10.1016/j.pnucene.2014.07.014

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：

In the last two years it was discovered that solubility of PuF3, UF4 and AmF3 in the eutectics LiF-NaF-KF are unexpectedly high (30 mol %, 45 mol % and 43 mol % correspondingly at 700 degrees C). This result opens the way for the development of the molten salt fast reactor with U-Pu nuclear fuel cycle (UPu-MSFR). The first calculations of the critical UPu-MSFR and subcritical MSR-burner of Am are presented. (C) 2014 Elsevier Ltd. All rights reserved.

引用

页码：33 / 36

页数：4