EXPERIMENTS AND CALCULATIONS ON NEUTRON STREAMING THROUGH BENT DUCTS

被引:7
作者
KLOOSTERMAN, JL
HOOGENBOOM, JE
ZSOLNAY, EM
机构
[1] DELFT UNIV TECHNOL, INTERFAC REACTOR INST, 2629 JB DELFT, NETHERLANDS
[2] TECH UNIV BUDAPEST, INST NUCL TECH, H-1521 BUDAPEST, HUNGARY
关键词
NEUTRON STREAMING; BENT DUCT; NEUTRON SPECTRA; BENCHMARK EXPERIMENT; NEUTRON FLUX; ANGULAR DISTRIBUTION; TRANSPORT CALCULATION; NEUTRON TRANSPORT; SPECTRUM UNFOLDING; 2-DIMENSIONAL DISCRETE-ORDINATES CALCULATION; MONTE-CARLO METHOD; SIMPLE FORMULA; DOT3.5; MORSE-SGC/S; SANDBP; IRIDUCT; COMPUTER CODES; COMPUTER CALCULATIONS;
D O I
10.3327/jnst.30.611
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
Neutron spectra in a cylindrical straight duct and in bent ducts with angles of 30-degrees, 60-degrees and 90-degrees have been measured by the multiple foil activation and thermoluminescence dosimetry methods. Two-dimensional discrete ordinates and three-dimensional Monte Carlo calculations are executed, and the results are compared with the measurements. The flow rate at the duct entrance calculated by the DOT3.5 code is underestimated by approximately 30%, due to a conversion of the core and reflector geometry from XY to RZ geometry. The fast neutron flux in the ducts is underestimated by 20% by the MORSE-SGC/S code due to a too coarse angular mesh of the source, which does not properly represent the actual angular distribution of the fast flux, which is highly peaked forwardly into the ducts. The thermal neutron flux was overestimated by the Monte Carlo calculation. A method is proposed to calculate the angular distribution of the flow rate at the duct entrance and to calculate the source strength and the angular distribution of the flow rate at the entrance of the second leg of the duct. The results are compared with those of the transport calculations. Generally, the agreement is quite satisfactory.
引用
收藏
页码:611 / 627
页数:17
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