You need JavaScript to view this

Calculational results for radiation embrittlement of WWER pressure vessel at the Kozloduy NPP

Abstract

Determination of radiation impact on metal state in the case of WWER-440/230 is made only by calculation methods since a special sample-witness (SW) incorporation had not been implemented. In WWER-1000 reactors such SW are foreseen but their spots are high above the active core. This is why in both reactors the appliance of a calculational procedure for radiation embrittlement determination is compulsory. The authors propose such a procedure accounting for the change in critical temperature of neutron brittleness by the neutron fluence. The neutron fluence and the shift of critical embrittlement temperature have been calculated for the maximum overloaded location and for the weld metal of the Kozloduy-5 and Kozloduy-6 reactors (WWER-1000). The shift of critical temperature in weld 4 of the Units 1-4 (WWER-440) is plotted versus work cycles and compared to experimental values. 4 figs., 5 tabs.
Authors:
Apostolov, T; Ilieva, K; Petrova, T [1] 
  1. Bylgarska Akademiya na Naukite, Sofia (Bulgaria). Inst. za Yadrena Izsledvaniya i Yadrena Energetika
Publication Date:
Dec 31, 1995
Product Type:
Miscellaneous
Report Number:
INIS-BG-0013; CONF-9410364-
Reference Number:
SCA: 210200; 360206; PA: AIX-28:034606; EDB-97:060726; SN: 97001775182
Resource Relation:
Conference: 1. scientific and technical conference on nuclear safety conference dedicated to NPP Kozloduy, Kozloduy (Bulgaria), 25-26 Oct 1994; Other Information: PBD: 1995; Related Information: Is Part Of Proceedings of a scientific-technical conference dedicated to the 20-th anniversary of Kozloduy NPP with international participation; PB: 442 p.
Subject:
21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS; 36 MATERIALS SCIENCE; KOZLODUY-1 REACTOR; NEUTRON FLUENCE; KOZLODUY-2 REACTOR; PRESSURE VESSELS; KOZLODUY-3 REACTOR; KOZLODUY-4 REACTOR; KOZLODUY-5 REACTOR; KOZLODUY-6 REACTOR; CRITICAL TEMPERATURE; EMBRITTLEMENT; RELIABILITY; THEORETICAL DATA; WELDED JOINTS
OSTI ID:
463261
Country of Origin:
Bulgaria
Language:
English
Other Identifying Numbers:
Other: ON: DE97621621; TRN: BG9600423034606
Availability:
INIS; OSTI as DE97621621
Submitting Site:
INIS
Size:
pp. 235-238
Announcement Date:

Citation Formats

Apostolov, T, Ilieva, K, and Petrova, T. Calculational results for radiation embrittlement of WWER pressure vessel at the Kozloduy NPP. Bulgaria: N. p., 1995. Web.
Apostolov, T, Ilieva, K, & Petrova, T. Calculational results for radiation embrittlement of WWER pressure vessel at the Kozloduy NPP. Bulgaria.
Apostolov, T, Ilieva, K, and Petrova, T. 1995. "Calculational results for radiation embrittlement of WWER pressure vessel at the Kozloduy NPP." Bulgaria.
@misc{etde_463261,
title = {Calculational results for radiation embrittlement of WWER pressure vessel at the Kozloduy NPP}
author = {Apostolov, T, Ilieva, K, and Petrova, T}
abstractNote = {Determination of radiation impact on metal state in the case of WWER-440/230 is made only by calculation methods since a special sample-witness (SW) incorporation had not been implemented. In WWER-1000 reactors such SW are foreseen but their spots are high above the active core. This is why in both reactors the appliance of a calculational procedure for radiation embrittlement determination is compulsory. The authors propose such a procedure accounting for the change in critical temperature of neutron brittleness by the neutron fluence. The neutron fluence and the shift of critical embrittlement temperature have been calculated for the maximum overloaded location and for the weld metal of the Kozloduy-5 and Kozloduy-6 reactors (WWER-1000). The shift of critical temperature in weld 4 of the Units 1-4 (WWER-440) is plotted versus work cycles and compared to experimental values. 4 figs., 5 tabs.}
place = {Bulgaria}
year = {1995}
month = {Dec}
}