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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2018.1
- 수록면
- 1,339 - 1,348 (10page)
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The aim of this paper is to determine neutronic performances of the light water reactor (LWR) spent fuelmixed with fertile thorium fuel in a FFHR. Time dependent three dimensional calculations for majortechnical data, such as blanket energy multiplication, tritium breeding ratio, cumulative fissile fuelenrichment and burnup have been performed by using Monte Carlo Neutron-Particle Transport codeMCNP5 1.4, coupled with a novel interface code MCNPAS, which is developed by our research group. Aself-sustaining tritium breeding ratio (TBR>1.05) has been kept throughout the calculations. The studyhas shown that the fissile fuel quality will be improved in the course of the transmutation of the LWRspent in the FFHR. The latter has gained the reusable fuel enrichment level conventional LWRs betweenone and two years. Furthermore, LWR spent fuel - thorium mixture provides higher burn-up values thanin light water reactors.
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참고문헌 (51)
참고문헌 신청
J.P. Freidberg / 2009 / Fusion fission hybrids revisited / Nat. Phys 5:370~372
W.W. Engle Jr. / 1970 / ANISN, a One-dimensional Discrete Ordinates Transport Code with Anisotropic Scattering
L.M. Petrie / SCALE5-SCALE system driver, NUREG/CR-0200, revision 7, volume III, section M1, ORNL/NUREG/CSD-2/V3/r7, Oak ridge national laboratory and SCALE 6.2.2, a comprehensive modeling and simulation suite for nuclear safety analysis and design / SCALE website
S. Şahin / 1991 / ERDEMLI, a Computer Program to Process ANISN Output Data
S. Şahin / 1989 / Investigation of the neutronic potential of moderated and fast (D, T) hybrid blankets for rejuvenation of CANDU spent fuel / Fusion Sci. Technol 16(3):331~345
W.W. Engle Jr. / 1970 / ANISN, a One-dimensional Discrete Ordinates Transport Code with Anisotropic Scattering
L.M. Petrie / SCALE5-SCALE system driver, NUREG/CR-0200, revision 7, volume III, section M1, ORNL/NUREG/CSD-2/V3/r7, Oak ridge national laboratory and SCALE 6.2.2, a comprehensive modeling and simulation suite for nuclear safety analysis and design / SCALE website
S. Şahin / 1991 / ERDEMLI, a Computer Program to Process ANISN Output Data
S. Şahin / 1989 / Investigation of the neutronic potential of moderated and fast (D, T) hybrid blankets for rejuvenation of CANDU spent fuel / Fusion Sci. Technol 16(3):331~345
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