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

Powers, Jeffrey J.¹  George, Nathan²  Maldonado, G. Ivan¹  Worrall, Andrew¹ 

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

关键词: 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;   

DOI  :  10.2172/1213354
RP-ID  :  ORNL/TM--2015/415
PID  :  OSTI ID: 1213354
Others  :  Other: AF5810000
Others  :  NEAF278

美国|英语

来源: SciTech Connect

【 摘 要 】

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)