Neutronic parameters of a low enrichment core in reactor LR-0 for MSR research
Result description
The study of the reactivity effects, which are in many cases negligible, is not a simple task. Consequently, the special core configuration with high sensitivity to low introduced reactivity changes was developed at LR-0 reactor. It proved to be suitablefor precise definition of any material, in terms of its impact on reactivity, being inserted into a reactor core. The results also imply this kind of core configuration to be applicable for the planed precise measurement of the MSR FLIBE salt temperature reactivity coefficients. This paper also examines the agreement between calculations and experiments for some cases of the low reactivity introduction into the core. Besides that, the similar cores can be used for purposes of neutron dosimetry, therefore the neutron spectrum in the experimental region was determined and compared with the results of MCNP calculations with the standard nuclear data libraries.
Keywords
LR-0 reactormolten salt reactorsCriticality safetySample irradiationNeutron spectroscopy
The result's identifiers
Result code in IS VaVaI
Alternative codes found
RIV/60162694:G43__/15:00523387
Result on the web
DOI - Digital Object Identifier
Alternative languages
Result language
angličtina
Original language name
Neutronic parameters of a low enrichment core in reactor LR-0 for MSR research
Original language description
The study of the reactivity effects, which are in many cases negligible, is not a simple task. Consequently, the special core configuration with high sensitivity to low introduced reactivity changes was developed at LR-0 reactor. It proved to be suitablefor precise definition of any material, in terms of its impact on reactivity, being inserted into a reactor core. The results also imply this kind of core configuration to be applicable for the planed precise measurement of the MSR FLIBE salt temperature reactivity coefficients. This paper also examines the agreement between calculations and experiments for some cases of the low reactivity introduction into the core. Besides that, the similar cores can be used for purposes of neutron dosimetry, therefore the neutron spectrum in the experimental region was determined and compared with the results of MCNP calculations with the standard nuclear data libraries.
Czech name
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Czech description
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Classification
Type
Jx - Unclassified - Peer-reviewed scientific article (Jimp, Jsc and Jost)
CEP classification
JF - Nuclear energy
OECD FORD branch
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Result continuities
Project
Continuities
P - Projekt vyzkumu a vyvoje financovany z verejnych zdroju (s odkazem do CEP)
Z - Vyzkumny zamer (s odkazem do CEZ)
Others
Publication year
2015
Confidentiality
S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů
Data specific for result type
Name of the periodical
Annals of Nuclear Energy
ISSN
0306-4549
e-ISSN
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Volume of the periodical
75
Issue of the periodical within the volume
January
Country of publishing house
GB - UNITED KINGDOM
Number of pages
7
Pages from-to
316-322
UT code for WoS article
000347493400039
EID of the result in the Scopus database
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Basic information
Result type
Jx - Unclassified - Peer-reviewed scientific article (Jimp, Jsc and Jost)
CEP
JF - Nuclear energy
Year of implementation
2015