Published April 1, 2009 | Version v1
Report

The Industrial Sodium Cooled Fast Reactor

Description

This paper investigates the use of enrichment and moderator zoning methods for optimizing the r-z power distribution within sodium cooled fast reactors. These methods allow overall greater fuel utilization in the core resulting in more fuel being irradiated near the maximum allowed thermal power. The peak-to-average power density was held to 1.18. This core design, in conjunction with a multiple-reheat Brayton power conversion system, has merit for producing an industrial level of electrical output (2400MWth, 1000MWe) from a relatively compact core size. The total core radius, including reflectors and shields, was held to 1.78m. Preliminary safety analysis suggests that positive reactivity insertion resulting from a leak between the sodium primary loop and helium power conversion system can be mitigated using simple gas-liquid centripetal separation strategies in the plant's primary loop.

Additional details

Publishing Information

Imprint Pagination
vp.
Report number
INL/CON--09-15519

Conference

Title
Advances in Nuclear Fuel Management IV
Dates
12-15 Apr 2009
Place
Hilton Head, SC (United States)

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
41016928
Subject category
S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
DESIGN; FAST REACTORS; HELIUM; MANAGEMENT; MODERATORS; NUCLEAR FUELS; POWER DENSITY; POWER DISTRIBUTION; REACTIVITY INSERTIONS; SAFETY ANALYSIS; SHIELDS; SODIUM
Descriptors DEC
ALKALI METALS; ELEMENTS; ENERGY SOURCES; EPITHERMAL REACTORS; FLUIDS; FUELS; GASES; MATERIALS; METALS; NONMETALS; RARE GASES; REACTOR MATERIALS; REACTORS

Optional Information

Contract/Grant/Project number
AC07-05ID14517
Funding organization
US Department of Energy (United States)