Burnup calculations using serpent code in accelerator driven thorium reactors
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Tarih
2013
Dergi Başlığı
Dergi ISSN
Cilt Başlığı
Yayıncı
Carl Hanser Verlag
Erişim Hakkı
info:eu-repo/semantics/closedAccess
Özet
In this study, burnup calculations have been performed for a sodium cooled Accelerator Driven Thorium Reactor (ADTR) using the Serpent 1.1.16 Monte Carlo code. The ADTR has been designed for burning minor actinides, mixed Th-232 and mixed U-233 fuels. A solid Pb-Bi spallation target in the center of the core is used and sodium as coolant. The system is designed for a heating power of 2 000 MW and for an operation time of 600 days. For burnup calculations the Advanced Matrix Exponential Method CRAM (Chebyshev Rational Approximation Method) and different nuclear data libraries (ENDF7, JEF2.2, JEFF3.1.1) were used. The effective multiplication factor change from 0.93 to 0.97 for different nuclear data libraries during the reactor operation period.
Açıklama
Anahtar Kelimeler
Kaynak
KERNTECHNIK
WoS Q Değeri
N/A
Scopus Q Değeri
Q3
Cilt
78
Sayı
3
