Report on Reactor Physics Assessment of Candidate Accident Tolerant Fuel Cladding Materials in LWRs

Technical Report · Fri Aug 28 00:00:00 EDT 2015

DOI:https://doi.org/10.2172/1213354· OSTI ID:1213354

Powers, Jeffrey J. ^[1]; George, Nathan ^[2]; Maldonado, G. Ivan ^[1]; Worrall, Andrew ^[1]

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1. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
2. Univ. of Tennessee, Knoxville, TN (United States)

This work focuses on ATF concepts being researched at Oak Ridge National Laboratory (ORNL), expanding on previous studies of using alternate cladding materials in pressurized water reactors (PWRs). The neutronic performance of two leading alternate cladding materials were assessed in boiling water reactors (BWRs): iron-chromium-aluminum (FeCrAl) cladding, and silicon carbide (SiC)-based composite cladding. This report fulfills ORNL Milestone M3FT-15OR0202332 within the fiscal year 2015 (FY15)

• Research Organization: Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
• Sponsoring Organization: USDOE Office of Nuclear Energy (NE)
• DOE Contract Number: AC05-00OR22725
• OSTI ID: 1213354
• Report Number(s): ORNL/TM-2015/415; AF5810000; NEAF278
• Country of Publication: United States
• Language: English

Related Subjects

nuclear
nuclear fuel
accident tolerant fuel
ATF
pressurized water reactor
PWR
boiling water reactor
BWR
NESTLE
FeCrAl
cladding
alternate cladding material
SiC
reactor physics
neutronics