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%2F68407700%3A21340%2F18%3A00317079" target="_blank" >RIV/68407700:21340/18:00317079 - isvavai.cz</a>
Alternative codes found
RIV/26722445:_____/18:N0000093
Result on the web
<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>
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 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.
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
S - Specificky vyzkum na vysokych skolach
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: 16th International Symposium
ISBN
978-0-8031-7661-4
ISSN
0066-0558
e-ISSN
—
Number of pages
14
Pages from-to
321-334
Publisher name
ASTM International
Place of publication
West Conshohocken
Event location
Santa Fe, NM
Event date
May 7, 2017
Type of event by nationality
WRD - Celosvětová akce
UT code for WoS article
000474939900029