Journal article Open Access

Neutron noise analysis of simulated mechanical and thermal-hydraulic perturbations in a PWR core

Torres L.A.; Chionis D.; Montalvo C.; Dokhane A.; García-Berrocal A.


MARC21 XML Export

<?xml version='1.0' encoding='UTF-8'?>
<record xmlns="http://www.loc.gov/MARC21/slim">
  <leader>00000nam##2200000uu#4500</leader>
  <datafield tag="041" ind1=" " ind2=" ">
    <subfield code="a">eng</subfield>
  </datafield>
  <datafield tag="653" ind1=" " ind2=" ">
    <subfield code="a">Noise analysis, neutron noise, Simulate 3K, mechanical perturbations, thermalhydraulic perturbations</subfield>
  </datafield>
  <controlfield tag="005">20181204153203.0</controlfield>
  <controlfield tag="001">1886859</controlfield>
  <datafield tag="700" ind1=" " ind2=" ">
    <subfield code="u">Paul Scherrer Institut, Laboratory for Reactor Physics and Thermal-Hydraulics</subfield>
    <subfield code="a">Chionis D.</subfield>
  </datafield>
  <datafield tag="700" ind1=" " ind2=" ">
    <subfield code="u">Energy and Fuels department, Technical University of Madrid (UPM)</subfield>
    <subfield code="a">Montalvo C.</subfield>
  </datafield>
  <datafield tag="700" ind1=" " ind2=" ">
    <subfield code="u">Paul Scherrer Institut, Laboratory for Reactor Physics and Thermal-Hydraulics</subfield>
    <subfield code="a">Dokhane A.</subfield>
  </datafield>
  <datafield tag="700" ind1=" " ind2=" ">
    <subfield code="u">Energy and Fuels department, Technical University of Madrid (UPM)</subfield>
    <subfield code="a">García-Berrocal A.</subfield>
  </datafield>
  <datafield tag="856" ind1="4" ind2=" ">
    <subfield code="s">2135981</subfield>
    <subfield code="z">md5:321cfbe774c70922896100112aeb4b9a</subfield>
    <subfield code="u">https://zenodo.org/record/1886859/files/pre_print.pdf</subfield>
  </datafield>
  <datafield tag="542" ind1=" " ind2=" ">
    <subfield code="l">open</subfield>
  </datafield>
  <datafield tag="260" ind1=" " ind2=" ">
    <subfield code="c">2018-12-03</subfield>
  </datafield>
  <datafield tag="909" ind1="C" ind2="O">
    <subfield code="p">openaire</subfield>
    <subfield code="p">openaire</subfield>
    <subfield code="p">openaire</subfield>
    <subfield code="o">oai:zenodo.org:1886859</subfield>
  </datafield>
  <datafield tag="909" ind1="C" ind2="4">
    <subfield code="c">121-252</subfield>
    <subfield code="v">126</subfield>
    <subfield code="p">Annals of Nuclear Energy</subfield>
  </datafield>
  <datafield tag="100" ind1=" " ind2=" ">
    <subfield code="u">Energy and Fuels department, Technical University of Madrid (UPM)</subfield>
    <subfield code="a">Torres L.A.</subfield>
  </datafield>
  <datafield tag="245" ind1=" " ind2=" ">
    <subfield code="a">Neutron noise analysis of simulated mechanical and thermal-hydraulic perturbations in a PWR core</subfield>
  </datafield>
  <datafield tag="536" ind1=" " ind2=" ">
    <subfield code="c">754316</subfield>
    <subfield code="a">Core monitoring techniques and experimental validation and demonstration</subfield>
  </datafield>
  <datafield tag="540" ind1=" " ind2=" ">
    <subfield code="u">http://creativecommons.org/licenses/by/4.0/legalcode</subfield>
    <subfield code="a">Creative Commons Attribution 4.0 International</subfield>
  </datafield>
  <datafield tag="650" ind1="1" ind2="7">
    <subfield code="a">cc-by</subfield>
    <subfield code="2">opendefinition.org</subfield>
  </datafield>
  <datafield tag="520" ind1=" " ind2=" ">
    <subfield code="a">&lt;p&gt;KWU-PWR plants show a high level of neutron noise that usually represents added problems in their operation. The frequency region of interest is below 1 Hz, so that thermohydraulic oscillations seem to be one of the main reasons behind. Nevertheless, recently, the neutron noise has experienced an increase in its normalized root mean square that coincide in time with the introduction of a new design of fuel assembly. This fact points out that there should be some relationship between neutron noise spectral characteristics and fuel assemblies&amp;rsquo; performance. In order to advance in understanding this phenomenon, the transient nodal code SIMULATE-3K (S3K) has been used to simulate mechanical vibrations of fuel assemblies and thermohydraulic oscillations of the core inlet flow. The simulated results obtained are neutron detectors signals which are analysed with noise analysis techniques and compared to real data.&lt;/p&gt;</subfield>
  </datafield>
  <datafield tag="773" ind1=" " ind2=" ">
    <subfield code="n">doi</subfield>
    <subfield code="i">isPreviousVersionOf</subfield>
    <subfield code="a">10.1016/j.anucene.2018.11.032</subfield>
  </datafield>
  <datafield tag="773" ind1=" " ind2=" ">
    <subfield code="n">doi</subfield>
    <subfield code="i">isVersionOf</subfield>
    <subfield code="a">10.5281/zenodo.1886858</subfield>
  </datafield>
  <datafield tag="024" ind1=" " ind2=" ">
    <subfield code="a">10.5281/zenodo.1886859</subfield>
    <subfield code="2">doi</subfield>
  </datafield>
  <datafield tag="980" ind1=" " ind2=" ">
    <subfield code="a">publication</subfield>
    <subfield code="b">article</subfield>
  </datafield>
</record>
9
12
views
downloads
All versions This version
Views 99
Downloads 1212
Data volume 25.6 MB25.6 MB
Unique views 99
Unique downloads 1212

Share

Cite as