Improvement of neutron source introduction method for absolute measurements of low reactor power

被引:2
|
作者
Yamamoto, T [1 ]
Miyoshi, Y [1 ]
机构
[1] Japan Atom Energy Res Inst, Dept Fuel Cycle Safety Res, Tokai, Ibaraki 3191195, Japan
关键词
neutron sources; introduction method; reactor power; calibration; critical assemblies; neutron transport calculation; Monte Carlo method; STACY;
D O I
10.1080/18811248.1999.9726299
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
The neutron source introduction method mas applied to absolute measurements of low reactor power at the Static Experiment Critical Facility STAGY, To obtain the effective neutron source intensity more accurately, which is a key parameter for the source introduction method, the neutron source is newly defined as fission neutrons from the first fission reaction caused by neutrons emitted from the external neutron source. To obtain the newly defined effective neutron source intensity, the probability that a neutron from the external neutron source causes a fission reaction is calculated using the Monte Carlo code MCNP. This calculation took into consideration the three-dimensional complicated core structures. Furthermore, the fission reaction distribution, fundamental mode forward and adjoint flux distribution in a critical state were calculated using the three-dimensional transport code THREEDANT. Following the principle of the neutron source introduction method. an external neutron source was inserted near the STAGY core tank and the reactor power was measured. The reactor powers by the neutron source introduction method were in good agreement with the ones from the analyses of the FP activity generated by high power operation.
引用
收藏
页码:1069 / 1075
页数:7
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