Criticality benchmark of VVER-1000 fresh fuel assembly with MCNP

S. M. Shauddin, M. S. Mahmood, M.J.H. Khan
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Abstract

IAEA benchmark problem for VVER-1000 reactor fresh fuel assemblies has been evaluated through Monte Carlo (MC) simulation. Infinite multiplication factor (k∞) values are calculated for different hexagonal fuel assemblies with 2 wt%, 3 wt%, 3.22 wt% and 3.3 wt% enriched U-235. MC simulations have been performed with the computer code MCNP at different temperatures 120°C, 278°C, 280°C, 302°C and 305°C for three different conditions: (i) 0 ppm soluble boron concentration, (ii) 1000 ppm soluble boron concentration, and (iii) full insertion of control rod clusters (absorber material, B4C) without boron in the moderator. The results are in good agreement with the deterministic calculations as reported in IAEA-TECDOC-847.
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带有MCNP的VVER-1000新燃料组件的临界基准
通过蒙特卡罗(MC)模拟对VVER-1000反应堆新燃料组件的IAEA基准问题进行了评估。计算了铀235浓度分别为2 wt%、3 wt%、3.22 wt%和3.3 wt%的不同六角形燃料组件的无限倍增因子(k∞)值。MC模拟已经用MCNP计算机代码在不同的温度下进行了120°C, 278°C, 280°C, 302°C和305°C三种不同的条件下进行:(i) 0 ppm可溶性硼浓度,(ii) 1000 ppm可溶性硼浓度,以及(iii)完全插入控制棒团(吸收材料,B4C)在慢化剂中没有硼。结果与IAEA-TECDOC-847报告的确定性计算结果吻合较好。
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期刊介绍: Today, nuclear reactors generate nearly one quarter of the electricity in nations representing two thirds of humanity, and other nuclear applications are integral to many aspects of the world economy. Nuclear fission remains an important option for meeting energy requirements and maintaining a balanced worldwide energy policy; with major countries expanding nuclear energy"s role and new countries poised to introduce it, the key issue is not whether the use of nuclear technology will grow worldwide, even if public opinion concerning safety, the economics of nuclear power, and waste disposal issues adversely affect the general acceptance of nuclear power, but whether it will grow fast enough to make a decisive contribution to the global imperative of sustainable development.
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