Estimation of Void Swelling in VVER-1000 Baffle Using Benchmark in LR-0 Reactor
The result's identifiers
Result code in 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>
Alternative codes found
RIV/68407700:21340/18:00317079
Result on the web
<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>
Alternative languages
Result language
angličtina
Original language name
Estimation of Void Swelling in VVER-1000 Baffle Using Benchmark in LR-0 Reactor
Original language description
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.
Czech name
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Czech description
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Classification
Type
D - Article in proceedings
CEP classification
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OECD FORD branch
20305 - Nuclear related engineering; (nuclear physics to be 1.3);
Result continuities
Project
Result was created during the realization of more than one project. More information in the Projects tab.
Continuities
P - Projekt vyzkumu a vyvoje financovany z verejnych zdroju (s odkazem do CEP)
Others
Publication year
2018
Confidentiality
S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů
Data specific for result type
Article name in the collection
Reactor Dosimetry: 16 th International Symposium, STP1608
ISBN
978-0-8031-7661-4
ISSN
—
e-ISSN
—
Number of pages
24
Pages from-to
321-334
Publisher name
ASTM International
Place of publication
West Conshohocken, PA, USA
Event location
Santa Fe, New Mexico, USA
Event date
May 12, 2017
Type of event by nationality
WRD - Celosvětová akce
UT code for WoS article
000474939900029