Published February 22, 2010 | Version v1
Miscellaneous

Lead-Cooled Fast Reactor (LFR) Design: Safety, Neutronics, Thermal Hydraulics, Structural Mechanics, Fuel, Core, and Plant Design

Description

The idea of developing fast spectrum reactors with molten lead (or lead alloy) as a coolant is not a new one. Although initially considered in the West in the 1950s, such technology was not pursued to completion because of anticipated difficulties associated with the corrosive nature of these coolant materials. However, in the Soviet Union, such technology was actively pursued during the same time frame (1950s through the 1980s) for the specialized role of submarine propulsion. More recently, there has been a renewal of interest in the West for such technology, both for critical systems as well as for Accelerator Driven Subcritical (ADS) systems. Meanwhile, interest in the former Soviet Union, primarily Russia, has remained strong and has expanded well beyond the original limited mission of submarine propulsion. This section reviews the past and current status of LFR development.

Availability note (English)

Available from https://e-reports-ext.llnl.gov/pdf/387560.pdf; PURL: https://www.osti.gov/servlets/purl/1020358-STFwvs/

Additional details

Publishing Information

Publisher
Springer
Imprint Place
Karlsruhe (Germany)
Imprint Pagination
100 p.
Report number
LLNL-BOOK--424323

INIS

Country of Publication
Germany
Country of Input or Organization
United States
INIS RN
42093241
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S43: PARTICLE ACCELERATORS;
Resource subtype / Literary indicator
Non-conventional Literature
Descriptors DEI
ACCELERATORS; COOLANTS; DESIGN; FAST REACTORS; LEAD ALLOYS; PROPULSION; SAFETY; SUBMARINES; THERMAL HYDRAULICS
Descriptors DEC
ALLOYS; EPITHERMAL REACTORS; FLUID MECHANICS; HYDRAULICS; MECHANICS; REACTORS; SHIPS

Optional Information

Contract/Grant/Project number
W-7405-ENG-48
Notes
A Compendium of Reactor Technology, Lead-Cooled Fast Reactor (LFR) Design: Safety, Neutronics, Thermal Hydraulics, Structural Mechanics, Fuel, Core, and Plant Design, 2010, pp. 2752-2769; PDF-FILE: 100; SIZE: 9.9 MBYTES
Funding organization
US Department of Energy (United States)