Prilog razvoju metodologija definiranja kriterija čepljenja cijevi generatora pare nuklearnih elektrana PWR tipa

Nadinić, Berislav (1997) Prilog razvoju metodologija definiranja kriterija čepljenja cijevi generatora pare nuklearnih elektrana PWR tipa. = Doctoral thesis , Sveučilište u Zagrebu, Fakultet strojarstva i brodogradnje, UNSPECIFIED. Mentor: Bogdan, Željko.

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Abstract (Croatian)

Čepljenje cijevi generatora pare na nuklearnim elektranama PWR tipa provodi se u svijetu, uglavnom uz primjenu konzervativnog kriterija čepljenja koji se temelji na dubini oštećenja cijevi. Ovakav pristup imao je za posljedicu veliki broj začepljenih cijevi koje su uzrokovale prijevremeno smanjenje snage nuklearnih elektrana, a katkad i zamjenu generatora pare. Ova disertacija definira metodologiju koja omogućuje primjenu različitih kriterija čepljenja na jednom generatoru pare, ovisno o lokaciji oštećenja odnosno mehanizmu degradacije. Takvi kriteriji čepljenja ovisni o lokaciji omogućuju bitno manji broj začepljenih cijevi tijekom redovnih obustava elektrana, time se odgađa smanjenje snage nuklearne elektrane za tri do osam godina. Razvijena metodologija definiranja kriterija uvodi, osim dubine oštećenja, i nove parametre kao npr. duljina oštećenja i volumen oštećenja preko kojih je također moguće kvalitetno definirati kriterije čepljenja. Pri tome je osnovna pretpostavka bila zadržati ili povećati razinu sigurnosti rada nuklearne elektrane u odnosu na stare kriterije, odnosno zadr2ati iii smanjiti vjerojatnost pucanja cijevi pri normalnom pogonu i u slučajevima nezgoda. Svi podaci koji se pri tom koriste, kao npr. lokacija i parametr oštećenja utvrđuju se ispitivanjima tehnikama vrtlo2nih struja. Metodologija definiranja kriterija čepljenja, ovisno o lokaciji, demonstrirana je na oštećenjima ispod potpornih plota na generatorima pare NE Krsko.

Abstract

Plugging of steam generator tubes in nuclear power plants of PWR type is performed in the world mainly on the basis of conservative plugging criteria based on depth of degradation. This approach caused great number of plugged tubes in many nuclear power plants and reduction of power and as well as on the end replacement of steam generators. This dissertation define methodology which assure applying of different plugging criteria on one steam generator which are location specific. Location specific means that every location or some group of locations in steam generator have different degradation processes which has to be treated from the standpoint of plugging criteria independently. Those location specific plugging criteria reduce significantly number of plugged tubes during regular shut downs, which indirectly prolong reduction of power for three to eight years. Developed methodology of plugging criteria introduces, except depth of degradation the other parameters like length and volume of degradation, which are also suitable for defining plugging criteria in some particular cases. The main objective during process of defining location specific plugging criteria was to maintain or to increase the level of safety of steam generator operation in normal operation and in accidental situations. All data which are used for definition of plugging criteria, like locations and parameters of degradation, are established through inspections based on eddy current methods and up to date techniques. Methodology of defining location specific plugging criteria was demonstrated on degradation under tube support plates of NPP Krsko steam generators.

Item Type: Thesis (Doctoral thesis)
Uncontrolled Keywords: generator pare; nuklearna elektrana; PWR tip
Keywords (Croatian): steam generator; nuclear power plants; PWR type
Divisions: 500 Department of Energy, Power Engineering and Environment > 510 Power Engineering and Energy Management Chair
Date Deposited: 22 Sep 2014 18:00
Last Modified: 16 Oct 2015 13:20
URI: http://repozitorij.fsb.hr/id/eprint/130

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