A neutronic program for critical and nonequilibrium study of mobile fuel reactors: The Cinsf1D code

被引：33

作者：

Lecarpentier, D ^{[1
]}

Carpentier, V ^{[1
]}

机构：

[1] Elect France, Res & Dev, Dept SINETICS, F-92141 Clamart, France

来源：

NUCLEAR SCIENCE AND ENGINEERING | 2003年 / 143卷 / 01期

关键词：

D O I：

10.13182/NSE03-A2316

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：

Molten salt reactors (MSRs) have the distinction of having a liquid fuel that is also the coolant. The transport of delayed-neutron precursors by the fuel modifies the precursors' equation. As a consequence, it is necessary to adapt the methods currently used for solid fuel reactors to achieve critical or kinetics calculations for an MSR. A program is presented for which this adaptation has been carried out within the framework of the two-energy-group diffusion theory with one dimension of space. This program has been called CinsfID (Cinetique pour reacteur a sels fondus ID).

引用

页码：33 / 46

页数：14

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