Estimation of Void Swelling in VVER-1000 Baffle Using Benchmark in LR-0 reactor

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F68407700%3A21340%2F18%3A00317079" target="_blank" >RIV/68407700:21340/18:00317079 - isvavai.cz</a>

Nalezeny alternativní kódy

RIV/26722445:_____/18:N0000093

Výsledek na webu

<a href="http://dx.doi.org/10.1520/STP760820770097" target="_blank" >http://dx.doi.org/10.1520/STP760820770097</a>

DOI - Digital Object Identifier

<a href="http://dx.doi.org/10.1520/STP760820770097" target="_blank" >10.1520/STP760820770097</a>

Jazyk výsledku

angličtina

Název v původním jazyce

Estimation of Void Swelling in VVER-1000 Baffle Using Benchmark in LR-0 reactor

Popis výsledku v původním jazyce

Reactor pressure vessel internals have a multipurpose task mainly to ensure optimal coolant flow, form and support active core, shield, guide and support of the in-core instrumentation. The VVER-1000 reactor internals are in the environment of high radiation doses, H3BO3 acid solved in water, high temperatures and gamma heating. These effects together with the high moderator flow rate form strongly inhomogeneous temperature fields in vessel internals and induced internal stresses. In case of VVER-1000 reactor baffle, the main potential limiting factor for the reactor operational lifetime prolongation is a void swelling of the Russian type titanium stabilized stainless 08Cr18Ni10Ti steel used to construct the baffle surrounding the active core. This paper presents a VVER-1000 mock-up model validation for the thermal neutron and gamma fluence in the region of the baffle, and a precise gamma heating and a displacements per atom (DPA) estimation in a 1/6 section of the reactor baffle. Obtained results on the mock-up are scaled to the VVER-1000 nominal power and used in ABAQUS code for void swelling estimation.

Název v anglickém jazyce

Estimation of Void Swelling in VVER-1000 Baffle Using Benchmark in LR-0 reactor

Popis výsledku anglicky

Reactor pressure vessel internals have a multipurpose task mainly to ensure optimal coolant flow, form and support active core, shield, guide and support of the in-core instrumentation. The VVER-1000 reactor internals are in the environment of high radiation doses, H3BO3 acid solved in water, high temperatures and gamma heating. These effects together with the high moderator flow rate form strongly inhomogeneous temperature fields in vessel internals and induced internal stresses. In case of VVER-1000 reactor baffle, the main potential limiting factor for the reactor operational lifetime prolongation is a void swelling of the Russian type titanium stabilized stainless 08Cr18Ni10Ti steel used to construct the baffle surrounding the active core. This paper presents a VVER-1000 mock-up model validation for the thermal neutron and gamma fluence in the region of the baffle, and a precise gamma heating and a displacements per atom (DPA) estimation in a 1/6 section of the reactor baffle. Obtained results on the mock-up are scaled to the VVER-1000 nominal power and used in ABAQUS code for void swelling estimation.

Druh

D - Stať ve sborníku

CEP obor

—

OECD FORD obor

20305 - Nuclear related engineering; (nuclear physics to be 1.3);

Projekt

Výsledek vznikl pri realizaci vícero projektů. Více informací v záložce Projekty.

Návaznosti

S - Specificky vyzkum na vysokych skolach

Rok uplatnění

2018

Kód důvěrnosti údajů

S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů

Název statě ve sborníku

Reactor Dosimetry: 16th International Symposium

ISBN

978-0-8031-7661-4

ISSN

0066-0558

e-ISSN

—

Počet stran výsledku

14

Strana od-do

321-334

Název nakladatele

ASTM International

Místo vydání

West Conshohocken

Místo konání akce

Santa Fe, NM

Datum konání akce

7. 5. 2017

Typ akce podle státní příslušnosti

WRD - Celosvětová akce

Kód UT WoS článku

000474939900029