|
|
|
|
LEADER |
00000nam a22000003u 4500 |
001 |
b10525071 |
003 |
CoU |
005 |
20180516222135.1 |
006 |
m o d f |
007 |
cr ||||||||||| |
008 |
190514e19970201||| o| f1|||||eng|d |
035 |
|
|
|a (TOE)ost467917
|
035 |
|
|
|a (TOE)467917
|
040 |
|
|
|a TOE
|c TOE
|
049 |
|
|
|a GDWR
|
072 |
|
7 |
|a 21
|2 edbsc
|
086 |
0 |
|
|a E 1.99:conf-9510423--
|
086 |
0 |
|
|a E 1.99:nureg/cp--0154
|
086 |
0 |
|
|a E 1.99: anl--96/14
|
086 |
0 |
|
|a E 1.99:nea/cnra/r--(96)1
|
086 |
0 |
|
|a E 1.99:conf-9510423--
|
088 |
|
|
|a conf-9510423--
|
088 |
|
|
|a nea/cnra/r--(96)1
|
088 |
|
|
|a anl--96/14
|
088 |
|
|
|a nureg/cp--0154
|
245 |
0 |
0 |
|a Defect specific maintenance of SG tubes -- How safe is it?
|h [electronic resource]
|
260 |
|
|
|a Richland, Wash. :
|b CH2M Hill, inc. ;
|a Oak Ridge, Tenn. :
|b distributed by the Office of Scientific and Technical Information, U.S. Department of Energy,
|c 1997.
|
300 |
|
|
|a pp. 525-532 :
|b digital, PDF file.
|
336 |
|
|
|a text
|b txt
|2 rdacontent.
|
337 |
|
|
|a computer
|b c
|2 rdamedia.
|
338 |
|
|
|a online resource
|b cr
|2 rdacarrier.
|
500 |
|
|
|a Published through SciTech Connect.
|
500 |
|
|
|a 02/01/1997.
|
500 |
|
|
|a "nureg/cp--0154"
|
500 |
|
|
|a " anl--96/14"
|
500 |
|
|
|a "nea/cnra/r--(96)1"
|
500 |
|
|
|a "conf-9510423--"
|
500 |
|
|
|a "TI97004312"
|
500 |
|
|
|a CNRA/CSNI workshop on steam generator tube integrity in nuclear power plants, Oak Brook, IL (United States), 30 Oct - 2 Nov 1995.
|
500 |
|
|
|a Cizelj, L.; Mavko, B.; Dvorsek, T. [Jozef Stefan Institute, Ljubljana (Slovenia)]
|
520 |
3 |
|
|a The efficiency of the defect specific plugging criterion for outside diameter stress corrosion cracking at tube support plates is assessed. The efficiency is defined by three parameters: (1) number of plugged tubes, (2) probability of steam generator tube rupture and (3) predicted accidental leak rate through the defects. A probabilistic model is proposed to quantify the probability of tube rupture, while procedures available in literature were used to define the accidental leak rates. The defect specific plugging criterion was then compared to the performance of traditional (45%) plugging criterion using realistic data from Krsko nuclear power plant. Advantages of the defect specific approach over the traditional one are clearly shown. Some hints on the optimization of safe life of steam generator are also given.
|
650 |
|
7 |
|a Tubes.
|2 local.
|
650 |
|
7 |
|a Defects.
|2 local.
|
650 |
|
7 |
|a Maintenance.
|2 local.
|
650 |
|
7 |
|a Steam Generators.
|2 local.
|
650 |
|
7 |
|a Evaluation.
|2 local.
|
650 |
|
7 |
|a Plugging.
|2 local.
|
650 |
|
7 |
|a Krsko Reactor.
|2 local.
|
650 |
|
7 |
|a Leaks.
|2 local.
|
650 |
|
7 |
|a Nuclear Power Reactors And Associated Plants.
|2 edbsc.
|
710 |
2 |
|
|a CH2M HILL (Firm).
|4 res.
|
710 |
1 |
|
|a United States.
|b Department of Energy.
|b Office of Scientific and Technical Information.
|4 dst.
|
856 |
4 |
0 |
|u http://www.osti.gov/scitech/biblio/467917
|z Online Access (via OSTI)
|
907 |
|
|
|a .b105250715
|b 03-09-23
|c 05-20-19
|
998 |
|
|
|a web
|b 05-20-19
|c f
|d m
|e p
|f eng
|g
|h 0
|i 1
|
956 |
|
|
|a Information bridge
|
999 |
f |
f |
|i 02d6b97d-2118-54a7-a801-69596928a2d3
|s d659d30a-8643-590c-99ec-543ef0eddcdd
|
952 |
f |
f |
|p Can circulate
|a University of Colorado Boulder
|b Online
|c Online
|d Online
|e E 1.99:conf-9510423--
|h Superintendent of Documents classification
|i web
|n 1
|