The influence of core power distribution on neutron flux density behind a pressure vessel of a VVER-1000 Mock Up in LR-0 reactor

被引：5

作者：

Kostal, Michal ^{[1
]}

Rypar, Vojtech ^{[1
]}

Losa, Evzen ^{[1
]}

Harut, David ^{[1
]}

Schulc, Martin ^{[1
]}

Klupak, Vit ^{[1
]}

Matej, Zdenek ^{[2
]}

Cvachovec, Frantisek ^{[3
]}

Jansky, Bohumil ^{[1
]}

Novak, Evzen ^{[1
]}

Czakoj, Tomas ^{[1
]}

Juricek, Vlastimil ^{[1
]}

Zaritsky, Sergey ^{[4
]}

机构：

[1] Res Ctr Rez, Husinec Rez 25068 130, Czech Republic

[2] Masaryk Univ, Bot 15, Brno 61200, Czech Republic

[3] Univ Def, Kounicova 65, Brno 61200, Czech Republic

[4] NRC Kurchatov Inst, 1 Kurchatov Sq, Moscow 123182, Russia

来源：

APPLIED RADIATION AND ISOTOPES | 2018年 / 142卷

关键词：

VVER-1000; Mock-Up; LR-0; Reactor dosimetry; Neutron spectrometry; RPV; BIOLOGICAL CONCRETE SHIELD; DEEP PENETRATION; NUCLEAR-DATA; SPECTRA; LIBRARY; SCIENCE;

D O I：

10.1016/j.apradiso.2018.09.005

中图分类号：

O61 [无机化学];

学科分类号：

070301 ; 081704 ;

摘要：

The neutron flux distribution behind a reactor pressure vessel (RPV) is an important parameter that is monitored to determine neutron fluence in the RPV. Together with mechanical testing of surveillance specimens, these are the most important parts of in-service inspection programs that are essential for a realistic and reliable assessment of the RPV residual lifetime. The fast neutron fluence values are determined by a calculation. These calculation results are accompanied by measurements of induced activities of the activation foils placed in the capsules behind the RPV at selected locations, namely in azimuthal profile. In case of discrepancies between the measured and calculated activities of the activation foils placed behind the pressure vessel, it is difficult to determine the source of the deviation. During such analysis, there arises a question on the influence of power peaking near core boundary on neutron profile behind the RPV. This paper compares the calculated and measured increase of the neutron flux density distribution behind the reactor pressure vessel in the azimuthal profile that has arisen from the replacement of 164 fuel pins located close to reactor internals by pins with the higher enrichment. This work can be understood as the first step in the characterization of the effect of incorrectly calculated pin power or burn-up in the fuel assembly at the core boundary relative to the neutron flux distribution behind reactor pressure vessel. Based on a good agreement between the calculated and experimental values, it can be concluded that the mathematical model used to evaluate the power increase is correct.

引用

页码：12 / 21

页数：10

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