On the Influence of Biological Shielding on Neutron Flux behind Reactor Pressure Vessel

被引:0
|
作者
Kostal, Michal [1 ]
Klupak, Vit [1 ]
Rypar, Vojtech [1 ]
Losa, Evzen [1 ]
Cvachovec, Frantisek [2 ]
Jansky, Bohumil [1 ]
Harutunyan, Davit [1 ]
Schulc, Martin [1 ]
Novak, Evzen [1 ]
Zaritskiy, Sergey M. [3 ]
Bresson, Anais [4 ]
Tommy-Martin, Michel [4 ]
Gosmain, Cecile-Aline [4 ]
机构
[1] Res Ctr Rez Ltd, Husinec Rez 25068 130, Czech Republic
[2] Univ Def, Kounicova 65, Brno 61200, Czech Republic
[3] RRC Kurchatov Inst, 1 Kurchatov Sq, Moscow 123182, Russia
[4] EDF R&D, 7 Blvd Gaspard Monge, F-91120 Palaiseau, France
来源
REACTOR DOSIMETRY: 16TH INTERNATIONAL SYMOSIUM | 2018年 / 1608卷
关键词
reactor dosimetry; room effect; neutron spectroscopy; VVER-1000; MOCK-UP; NUCLEAR-SCIENCE; EMBRITTLEMENT; TRANSPORT; LIBRARY;
D O I
10.1520/STP760820170079
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 flux behind the reactor pressure vessel (RPV) is formed by primary transmitted neutrons from the core and also by backscattered neutrons from biological shielding. In the evaluations of neutron flux in the RPV, the knowledge of the reflected neutrons' share on the total flux is important for correct assessment of possible discrepancies. This paper aims to determine the share of backscattered neutrons in the spectrum behind the RPV and presents new results obtained with an improved fixed source model based on more precise and validated power distribution. Measurements of fast and thermal neutron fluxes in various configurations of biological shielding are realized in a VVER-1000 mock-up in the LR-0 reactor. Additionally, the calculations of the VVER-1000 mock-up are supplemented by calculations of an Electricite de France heavy reflector benchmark that represents arbitrary pressurized water reactor geometry. Comparison of both types of results shows that the LR-0 mock-up measurements are directly applicable, in terms of reactor dosimetry, to other types of pressurized water reactors, regardless of the burn-up and type of fuel they use. It is shown that the amount of backscattered thermal neutrons behind the reactor vessel strongly depends on the distance between the vessel and the concrete shielding. The choice of the data library for calculations influences the results in the thermal region as well.
引用
收藏
页码:308 / 320
页数:13
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