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%2F26722445%3A_____%2F18%3AN0000093" target="_blank" >RIV/26722445:_____/18:N0000093 - isvavai.cz</a>

Nalezeny alternativní kódy

RIV/68407700:21340/18:00317079

Výsledek na webu

<a href="https://www.astm.org/DIGITAL_LIBRARY/STP/PAGES/STP160820170091.htm" target="_blank" >https://www.astm.org/DIGITAL_LIBRARY/STP/PAGES/STP160820170091.htm</a>

DOI - Digital Object Identifier

<a href="http://dx.doi.org/10.1520/STP160820170091" target="_blank" >10.1520/STP160820170091</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 that is mainly to ensure optimal coolant flow, to form and support the active core, and to shield, guide, and support the in-core instrumentation. The VVER-1000 reactor internal components are in an environment with high radiation doses, boric (H3BO3) acid dissolved in water, high temperatures, and gamma heating. These effects, together with the high moderator flow rate, form strongly inhomogeneous temperature fields in vessel internal components and induced internal stresses. In the case of the VVER-1000 reactor baffle, the main potential limiting factor for prolongation of the reactor operational lifetime 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 as well as a displacement-per-atom estimation in a one-sixth 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 that is mainly to ensure optimal coolant flow, to form and support the active core, and to shield, guide, and support the in-core instrumentation. The VVER-1000 reactor internal components are in an environment with high radiation doses, boric (H3BO3) acid dissolved in water, high temperatures, and gamma heating. These effects, together with the high moderator flow rate, form strongly inhomogeneous temperature fields in vessel internal components and induced internal stresses. In the case of the VVER-1000 reactor baffle, the main potential limiting factor for prolongation of the reactor operational lifetime 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 as well as a displacement-per-atom estimation in a one-sixth 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

P - Projekt vyzkumu a vyvoje financovany z verejnych zdroju (s odkazem do CEP)

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: 16 th International Symposium, STP1608

ISBN

978-0-8031-7661-4

ISSN

—

e-ISSN

—

Počet stran výsledku

24

Strana od-do

321-334

Název nakladatele

ASTM International

Místo vydání

West Conshohocken, PA, USA

Místo konání akce

Santa Fe, New Mexico, USA

Datum konání akce

12. 5. 2017

Typ akce podle státní příslušnosti

WRD - Celosvětová akce

Kód UT WoS článku

000474939900029