Analysis of uranium oxide fuel transmutation in VVER-1000 reactor using VISTA and WIMS-D4 codes

被引：2

作者：

Abbasi, Akbar ^{[1
,2
]}

机构：

[1] Univ Kyrenia, Via Mersin 10, TR-99320 Girne, North Cyprus, Turkey

[2] Nucl Sci & Technol Inst NSTRI, Tehran, Iran

来源：

NUCLEAR ENGINEERING AND DESIGN | 2018年 / 328卷

关键词：

VVER-1000; Spent fuel; VISTA; ORIGEN; WIMS; Fission product; MINOR ACTINIDE TRANSMUTATION; BED NUCLEAR-REACTOR; CANDU REACTORS; CRITICALITY; PLUTONIUM; CORE;

D O I：

10.1016/j.nucengdes.2018.01.005

中图分类号：

TL [原子能技术]; O571 [原子核物理学];

学科分类号：

0827 ; 082701 ;

摘要：

In this study, the front end and back end of Uranium Oxide (UOX) fuel cycle were first calculated using nuclear fuel cycle simulation system (VISTA) code. The front end calculated values are 19595.3 ton/year for ore-U, 196 ton/year for natural-U, 196 ton/year for UF6, 111.4 metric ton separative work unit (MTSWU) for enrichment requirements, 172.211 ton/year depleted-U and 23.8 ton/year for Fresh Fuel (FF) requirements. The back end calculated values were 23.8 ton/year for Spent Fuel (SF), 0.024 ton/year for Actinide Inventory (AI) and 0.981 ton/year for Fission Product (FP) isotopes. After that the transmutation of UOX fuel results calculated by VISTA benchmarked with WIMS-D4 code. The calculations carried out in 30,000, 35,000, 40,000 and 45,000 MWd/tHM discharge burnup stages. The comparison of results showed that variance was less than 15%.

引用

页码：115 / 120

页数：6

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