Sensitivity Analysis of Stainless Steel Reflector for VR-1 Training Reactor
Identifikátory výsledku
Kód výsledku v IS VaVaI
<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F68407700%3A21340%2F20%3A00351429" target="_blank" >RIV/68407700:21340/20:00351429 - isvavai.cz</a>
Výsledek na webu
<a href="https://doi.org/10.1051/epjconf/202124708003" target="_blank" >https://doi.org/10.1051/epjconf/202124708003</a>
DOI - Digital Object Identifier
<a href="http://dx.doi.org/10.1051/epjconf/202124708003" target="_blank" >10.1051/epjconf/202124708003</a>
Alternativní jazyky
Jazyk výsledku
angličtina
Název v původním jazyce
Sensitivity Analysis of Stainless Steel Reflector for VR-1 Training Reactor
Popis výsledku v původním jazyce
Pressurized water reactors are typically surrounded in the radial direction by neutron reflectors made from stainless steel and water. These reflectors decrease neutron leakage and provide protection of pressure vessel from fast neutrons damaging its integrity. Such a radial reflector influences multiplication factor of the core and distribution of neutron flux and fission power inside the core. All these effects can be analyzed by full-core simulations using macroscopic constants. Methodology for generation of the macroscopic constants for non-fuel regions will be tested for new stainless steel reflectors at the VR-1 reactor. Rods from SS 304l material will be used for construction of radial reflectors for the VR-1 reactor. They will be design to generate sufficient measurable response in selected core characteristics. The study is focused on core power distribution and reactivity worth of absorbing rods in a VR-1 reactor core. The core typically consists of about 20 IRT-4M fuel assemblies and seven absorbing rods UR-70. Replacing water surrounding the core by several reflector assemblies containing stainless steel will influence leakage and distribution of neutrons inside the core. The current analysis deals with local effects and employs the sensitivity study to discover the nature of reflectors’ impact on the reactor core. These effects were studied even for several past VR-1 reactor core configurations. All calculations were carried out in Serpent2 Monte-Carlo code with various evaluated libraries: ENDF/B-VII.1, ENDF/B-VIII.0, and JEFF-3.3 data.
Název v anglickém jazyce
Sensitivity Analysis of Stainless Steel Reflector for VR-1 Training Reactor
Popis výsledku anglicky
Pressurized water reactors are typically surrounded in the radial direction by neutron reflectors made from stainless steel and water. These reflectors decrease neutron leakage and provide protection of pressure vessel from fast neutrons damaging its integrity. Such a radial reflector influences multiplication factor of the core and distribution of neutron flux and fission power inside the core. All these effects can be analyzed by full-core simulations using macroscopic constants. Methodology for generation of the macroscopic constants for non-fuel regions will be tested for new stainless steel reflectors at the VR-1 reactor. Rods from SS 304l material will be used for construction of radial reflectors for the VR-1 reactor. They will be design to generate sufficient measurable response in selected core characteristics. The study is focused on core power distribution and reactivity worth of absorbing rods in a VR-1 reactor core. The core typically consists of about 20 IRT-4M fuel assemblies and seven absorbing rods UR-70. Replacing water surrounding the core by several reflector assemblies containing stainless steel will influence leakage and distribution of neutrons inside the core. The current analysis deals with local effects and employs the sensitivity study to discover the nature of reflectors’ impact on the reactor core. These effects were studied even for several past VR-1 reactor core configurations. All calculations were carried out in Serpent2 Monte-Carlo code with various evaluated libraries: ENDF/B-VII.1, ENDF/B-VIII.0, and JEFF-3.3 data.
Klasifikace
Druh
D - Stať ve sborníku
CEP obor
—
OECD FORD obor
20305 - Nuclear related engineering; (nuclear physics to be 1.3);
Návaznosti výsledku
Projekt
<a href="/cs/project/EF16_013%2F0001790" target="_blank" >EF16_013/0001790: Posílení a rozvoj výzkumu na ČVUT v Praze s využitím výzkumné infrastruktury VR-1- Školní reaktor pro výzkumnou činnost</a><br>
Návaznosti
P - Projekt vyzkumu a vyvoje financovany z verejnych zdroju (s odkazem do CEP)<br>S - Specificky vyzkum na vysokych skolach
Ostatní
Rok uplatnění
2020
Kód důvěrnosti údajů
S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů
Údaje specifické pro druh výsledku
Název statě ve sborníku
PHYSOR2020 conference proceedings
ISBN
9781713827245
ISSN
—
e-ISSN
—
Počet stran výsledku
8
Strana od-do
1578-1585
Název nakladatele
Cambridge University Engineering Department
Místo vydání
Cambridge
Místo konání akce
Cambridge
Datum konání akce
30. 3. 2020
Typ akce podle státní příslušnosti
WRD - Celosvětová akce
Kód UT WoS článku
—