Published 2009 | Version v1
Miscellaneous Restricted

Neutronic analysis of two-fluid thorium molten salt reactor

  • 1. Nuclear Research Institute Rez, Rez (Czech Republic)

Description

The aim of this paper is to evaluate features of the two-fluid MSBR through a parametric study and compare its properties to one-fluid MSBR concepts. The starting point of the analysis is the original ORNL 1000 MWe reactor design, although simplified to some extent. We studied the influence of dimensions of distinct reactor parts - fuel and fertile channels radius, plenum height, design etc. - on fundamental reactor properties: breeding ratio and doubling time, reactor inventory, graphite lifetime, and temperature feedback coefficients. The calculations were carried out using MCNP5 code. Based on obtained results we proposed an improved reactor design. Our results show clear advantages of the concept with two separate fluoride salts if compared to the one fluid concept in breading, doubling time, and temperature feedback coefficients. Limitations of the two-fluid concept - particularly the graphite lifetime - are also pointed out. The reactor design can be a subject of further optimizations, namely from the viewpoint of reactor safety. (author)

Files

Restricted

The record is publicly accessible, but files are restricted to users with access.

Part of:
Proceedings of 2009 international congress on advances in nuclear power plants

Additional details

Publishing Information

Imprint Title
Proceedings of 2009 international congress on advances in nuclear power plants
Imprint Pagination
[2572 p.]
Journal Page Range
[6 p.]
Report number
INIS-JP--123

Conference

Title
2009 international congress on advances in nuclear power plants
Acronym
ICAPP2009
Dates
10-14 May 2009
Place
Tokyo (Japan)

Optional Information

Notes
Available as CD-ROM Data in PDF format, Folder Name: FinalPaper, Paper ID: 9384.pdf; 6 refs., 4 figs., 6 tabs.