Sensitivity Analysis of Stainless Steel Reflector for VR-1 Training Reactor

Result code in 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>

Result on the web

<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>

Result language

angličtina

Original language name

Sensitivity Analysis of Stainless Steel Reflector for VR-1 Training Reactor

Original language description

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.

Czech name

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Czech description

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Type

D - Article in proceedings

CEP classification

—

OECD FORD branch

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

Project

<a href="/en/project/EF16_013%2F0001790" target="_blank" >EF16_013/0001790: Strengthening and development of research at Czech Technical University in Prague with the use of research infrastructure VR?1 Training Reactor for research activities</a><br>

Continuities

P - Projekt vyzkumu a vyvoje financovany z verejnych zdroju (s odkazem do CEP)<br>S - Specificky vyzkum na vysokych skolach

Publication year

2020

Confidentiality

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

Article name in the collection

PHYSOR2020 conference proceedings

ISBN

9781713827245

ISSN

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e-ISSN

—

Number of pages

8

Pages from-to

1578-1585

Publisher name

Cambridge University Engineering Department

Place of publication

Cambridge

Event location

Cambridge

Event date

Mar 30, 2020

Type of event by nationality

WRD - Celosvětová akce

UT code for WoS article

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