TY - JOUR
T1 - Principle of rationalizing the criteria for abnormal transients of the Super LWR with fuel rod analyses
AU - Yamaji, A.
AU - Oka, Y.
AU - Ishiwatari, Y.
AU - Liu, J.
AU - Suzuki, M.
PY - 2006/8
Y1 - 2006/8
N2 - A detailed fuel rod design is carried out for the first time in the development of Supercritical-pressure Light Water Reactor (Super LWR). The fuel rod design is similar to that of LWR, consisting of UO2 pellets, a gas plenum and a Stainless Steel Cladding. The principle of rationalizing the criteria for abnormal transients of the Super LWR is developed. The fuel rod integrities can be assured by preventing plastic strains on the cladding, preventing the cladding buckling collapse, and keeping the pellet centerline temperature below its melting point. The FEMAXI-6 fuel analysis code is used to evaluate the fuel rod integrities in abnormal transient conditions. Detailed analyses have shown that allowable limits to the maximum fuel rod power and maximum cladding temperature can be determined to assure the fuel integrities. These limits may be useful in the plant safety analyses to confirm the fuel integrities during abnormal transients.
AB - A detailed fuel rod design is carried out for the first time in the development of Supercritical-pressure Light Water Reactor (Super LWR). The fuel rod design is similar to that of LWR, consisting of UO2 pellets, a gas plenum and a Stainless Steel Cladding. The principle of rationalizing the criteria for abnormal transients of the Super LWR is developed. The fuel rod integrities can be assured by preventing plastic strains on the cladding, preventing the cladding buckling collapse, and keeping the pellet centerline temperature below its melting point. The FEMAXI-6 fuel analysis code is used to evaluate the fuel rod integrities in abnormal transient conditions. Detailed analyses have shown that allowable limits to the maximum fuel rod power and maximum cladding temperature can be determined to assure the fuel integrities. These limits may be useful in the plant safety analyses to confirm the fuel integrities during abnormal transients.
UR - http://www.scopus.com/inward/record.url?scp=33747876240&partnerID=8YFLogxK
UR - http://www.scopus.com/inward/citedby.url?scp=33747876240&partnerID=8YFLogxK
U2 - 10.1016/j.anucene.2006.05.010
DO - 10.1016/j.anucene.2006.05.010
M3 - Article
AN - SCOPUS:33747876240
SN - 0306-4549
VL - 33
SP - 984
EP - 993
JO - Annals of Nuclear Energy
JF - Annals of Nuclear Energy
IS - 11-12
ER -