Published 2006
| Version v1
Book
Assessment of deep burnup concept based on graphite moderated gas-cooled thermal reactor
Creators
- 1. Argonne National Laboratory, 9700 South Cass Avenue, Argonne, IL 60439 (United States)
- 2. General Atomics, P. O. Box 85608, San Diego, CA (United States)
Description
A systematic assessment of the General Atomics (GA) proposed one-pass and two-pass deep-burn concepts based on the modular helium-cooled reactor design (DB-MHR) using non-uranium fuel has been performed. Sensitivity studies are done to investigate the impact of core design parameters and concept on the transmutation performance (maximum of 60% destruction). The repository loading benefits arising from the DB-MHR and LWR Inert Matrix Fuel (IMF) concepts are also estimated and compared (∼2.0 and 1.6, respectively). (authors)
Additional details
Publishing Information
- Publisher
- American Nuclear Society - ANS
- Imprint Place
- La Grange Park (United States)
- ISBN
- 0-89448-697-7
- Imprint Pagination
- 12 p.
Conference
- Title
- American Nuclear Society's Topical Meeting on Reactor Physics - Advances in Nuclear Analysis and Simulation
- Acronym
- PHYSOR-2006
- Dates
- 10-14 Sep 2006
- Place
- Vancouver, BC (Canada)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 43129965
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BURNUP; DESIGN; FUEL ELEMENTS; GRAPHITE MODERATED REACTORS; HELIUM COOLED REACTORS; MATRIX MATERIALS; REACTOR CORES; SENSITIVITY ANALYSIS; THERMAL REACTORS
- Descriptors DEC
- GAS COOLED REACTORS; MATERIALS; REACTOR COMPONENTS; REACTORS
Optional Information
- Notes
- 7 refs.