Detail publikačního výsledku

COMPARISON BETWEEN SIMULATION AND MEASUREMENT OF NEUTRON FLUX USING 59Co AT THE SPALLATION TARGET QUINTA

ZEMAN, M.; ADAM, J.; KATOVSKÝ, K.; SVOBODA, J.; VESPALEC, R.; KOLEKTIV, S.

Originální název

COMPARISON BETWEEN SIMULATION AND MEASUREMENT OF NEUTRON FLUX USING 59Co AT THE SPALLATION TARGET QUINTA

Anglický název

COMPARISON BETWEEN SIMULATION AND MEASUREMENT OF NEUTRON FLUX USING 59Co AT THE SPALLATION TARGET QUINTA

Druh

Stať ve sborníku v databázi WoS či Scopus

Originální abstrakt

Experiment with the natural uranium spallation target called QUINTA was performed at the Joint Institute for Nuclear Research (JINR) in December 2013. The mass of the QUINTA setup is 512 kg. It consists of five hexagonal sections. The samples of Co-59 have been irradiated with deuteron beam in the field of secondary neutrons at the Nuclotron accelerator from JINR. Energy of the deuteron beam was 4 AGeV. The total beam integral was 6.1(6)E+12. During the experiment, samples were situated in different position inside the assembly and after irradiation were transported to the spectroscopy laboratory and measured at the high-purity germanium semiconductor detectors. The experimental neutron flux was determined and compared with calculated reaction rates with the MCNPX 2.6 and MCNPX 2.7 codes.

Anglický abstrakt

Experiment with the natural uranium spallation target called QUINTA was performed at the Joint Institute for Nuclear Research (JINR) in December 2013. The mass of the QUINTA setup is 512 kg. It consists of five hexagonal sections. The samples of Co-59 have been irradiated with deuteron beam in the field of secondary neutrons at the Nuclotron accelerator from JINR. Energy of the deuteron beam was 4 AGeV. The total beam integral was 6.1(6)E+12. During the experiment, samples were situated in different position inside the assembly and after irradiation were transported to the spectroscopy laboratory and measured at the high-purity germanium semiconductor detectors. The experimental neutron flux was determined and compared with calculated reaction rates with the MCNPX 2.6 and MCNPX 2.7 codes.

Klíčová slova

threshold activation detectors; neutron flux

Klíčová slova v angličtině

threshold activation detectors; neutron flux

Autoři

ZEMAN, M.; ADAM, J.; KATOVSKÝ, K.; SVOBODA, J.; VESPALEC, R.; KOLEKTIV, S.

Rok RIV

2018

Vydáno

31.01.2017

Nakladatel

JINR

Místo

Dubna, JINR

ISBN

978-5-9530-0416-9

Kniha

The XX International Scientific Conference of Young Scientists and Specialists (AYSS-2016)

Strany od

234

Strany do

238

Strany počet

307

BibTex

@inproceedings{BUT140924,
  author="Miroslav {Zeman} and Jindřich {Adam} and Karel {Katovský} and Josef {Svoboda} and Radek {Vespalec} and Spoluautorů {Kolektiv}",
  title="COMPARISON BETWEEN SIMULATION AND MEASUREMENT OF NEUTRON FLUX USING 59Co AT THE SPALLATION TARGET QUINTA",
  booktitle="The XX International Scientific Conference of Young Scientists and Specialists (AYSS-2016)",
  year="2017",
  pages="234--238",
  publisher="JINR",
  address="Dubna, JINR",
  isbn="978-5-9530-0416-9"
}