Published February 2001 | Version v1
Report Open

Fuel cycle of BREST-1200 with non-proliferation of plutonium and equivalent disposal of radioactive waste

  • 1. Research and Development Institute of Power Engineering, Moscow (Russian Federation)

Description

Depletion of hydrocarbon resources and concerns regarding greenhouse gas emissions are expected to lead to increased reliance on nuclear power in the Russian Federation in the 21st century. Increased reliance on nuclear power for electricity production is best achieved using innovative reactor designs and fuel cycles that are more efficient, inherently safe, proliferation resistant and produce less long lived radioactive waste. The BREST series of reactors is being developed in the Russian Federation to meet these criteria. The current state of development work on the BREST-1200 reactor is described. (author)

Files

32041330.pdf

Files (113.4 kB)

Name Size Download all
md5:48fd0b8d69dc403f3ff1f648049ba2d4
113.4 kB Preview Download
Part of:
Technologies for the management of radioactive waste from nuclear power plants and back end nuclear fuel cycle activities. Proceedings

Additional details

Publishing Information

Imprint Title
Technologies for the management of radioactive waste from nuclear power plants and back end nuclear fuel cycle activities. Proceedings
Imprint Pagination
[627 p.]
Journal Issue
no. 6/C
Series
C and S papers series
Journal Page Range
[7 p.]
ISSN
1562-4153
Report number
IAEA-CSP--6/C

Conference

Title
International symposium on technologies for the management of radioactive waste from nuclear power plants and back end nuclear fuel cycle activities
Dates
30 Aug - 3 Sep 1999
Place
Taejon (Korea, Republic of)

Optional Information

Notes
2 figs Imprint:Data in PDF format; Acrobat Reader for Windows 3.x, 95, 98, NT 3.5.1, NT 4.0, MacIntosh and UNIX (SUN, HP, IRIX (SGI), AIX and Digital UNIX) included
Secondary number(s)
IAEA-SM--357/48P