Precision Calculations of Some Neutron-Physical Characteristics of VVER-1000 Using the MCU Code

被引:3
|
作者
Bikeev, A. S. [1 ]
机构
[1] Natl Res Ctr Kurchatov Inst, Moscow, Russia
关键词
Fuel Element; Fuel Assembly; Fuel Load; Nominal Power; Fuel Temperature;
D O I
10.1007/s10512-015-9985-6
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
Highly detailed computational models of the reactors in the Nos. 2 and 3 units at the Rostov NPP and the No. 3 unit at the Tianwan NPP (China) with the first fuel load are briefly described. Calculations of two states of the reactors were performed with the MCU code, implementing the Monte Carlo method, for each model: at the lowest controllable power and at nominal power. A TPA thermophysical module connected to the MCU code was used to take account of feedbacks in calculating the state of the reactor at nominal power. Analysis of the results obtained using the MCU and BIPR-7A codes showed agreement between the main characteristics of the reactor facilities.
引用
收藏
页码:234 / 237
页数:4
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