Measurement and calculation of fast neutron and gamma spectra
in well defined cores in LR-0 reactor

J 2017

Measurement and calculation of fast neutron and gamma spectra in well defined cores in LR-0 reactor

KOŠŤÁL, Michal; Zdeněk MATĚJ; František CVACHOVEC; Vojtěch RYPAR; Evžen LOSA et al.

Základní údaje

Originální název

Measurement and calculation of fast neutron and gamma spectra in well defined cores in LR-0 reactor

Autoři

KOŠŤÁL, Michal; Zdeněk MATĚJ ; František CVACHOVEC; Vojtěch RYPAR; Evžen LOSA; Jiří REJCHRT; Filip MRAVEC a Martin VEŠKRNA

Vydání

Applied Radiation and Isotopes, Elsevier, 2017, 0969-8043

Další údaje

Jazyk

angličtina

Typ výsledku

Článek v odborném periodiku

Obor

10201 Computer sciences, information science, bioinformatics

Stát vydavatele

Nizozemské království

Utajení

není předmětem státního či obchodního tajemství

Odkazy

URL

Impakt faktor

Impact factor: 1.123

Označené pro přenos do RIV

Ano

Kód RIV

RIV/00216224:14330/17:00095937

Organizační jednotka

Fakulta informatiky

Klíčová slova anglicky

LR-0; Neutron spectra; Cross section validation; Detector calibration; Zero power reactor utilization; Reactor Dosimetry

Změněno: 31. 5. 2022 17:32, RNDr. Pavel Šmerk, Ph.D.

Anotace

V originále

A well-defined neutron spectrum is essential for many types of experimental topics and is also important for both calibration and testing of spectrometric and dosimetric detectors. Provided it is well described, such a spectrum can also be employed as a reference neutron field that is suitable for validating selected cross sections. The present paper aims to compare calculations and measurements of such a well-defined spectra in geometrically similar cores of the LR-0 reactor with fuel containing slightly different enrichments (2 %, 3.3% and 3.6 %). The common feature to all cores is a centrally located dry channel which can be used for the insertion of studied materials. The calculation of neutron and gamma spectra was realized with the MCNP6 code using ENDF/B-VII.0, JEFF-3.1, JENDL-3.3, ROSFOND-2010 and CENDL-3.1 nuclear data libraries. Only minor differences in neutron and gamma spectra were found in the comparison of the presented reactor cores with different fuel enrichments. One exception is the gamma spectrum in the higher energy region (above 8 MeV), where more pronounced variations could be observed.

Citovat

KOŠŤÁL, Michal; Zdeněk MATĚJ; František CVACHOVEC; Vojtěch RYPAR; Evžen LOSA; Jiří REJCHRT; Filip MRAVEC a Martin VEŠKRNA. Measurement and calculation of fast neutron and gamma spectra in well defined cores in LR-0 reactor. Applied Radiation and Isotopes. Elsevier, 2017, roč. 120, č. 1, s. 45-50. ISSN 0969-8043. Dostupné z: https://doi.org/10.1016/j.apradiso.2016.11.004.

@article{1361984,
   author = {Košťál, Michal and Matěj, Zdeněk and Cvachovec, František and Rypar, Vojtěch and Losa, Evžen and Rejchrt, Jiří and Mravec, Filip and Veškrna, Martin},
   article_number = {1},
   doi = {https://doi.org/10.1016/j.apradiso.2016.11.004},
   keywords = {LR-0; Neutron spectra; Cross section validation; Detector calibration; Zero power reactor utilization; Reactor Dosimetry},
   language = {eng},
   issn = {0969-8043},
   journal = {Applied Radiation and Isotopes},
   title = {Measurement and calculation of fast neutron and gamma spectra in well defined cores in LR-0 reactor},
   url = {http://dx.doi.org/10.1016/j.apradiso.2016.11.004},
   volume = {120},
   year = {2017}
}

TY  - JOUR
ID  - 1361984
AU  - Košťál, Michal - Matěj, Zdeněk - Cvachovec, František - Rypar, Vojtěch - Losa, Evžen - Rejchrt, Jiří - Mravec, Filip - Veškrna, Martin
PY  - 2017
TI  - Measurement and calculation of fast neutron and gamma spectra in well defined cores in LR-0 reactor
JF  - Applied Radiation and Isotopes
VL  - 120
IS  - 1
SP  - 45-50
EP  - 45-50
PB  - Elsevier
SN  - 09698043
KW  - LR-0
KW  - Neutron spectra
KW  - Cross section validation
KW  - Detector calibration
KW  - Zero power reactor utilization
KW  - Reactor Dosimetry
UR  - http://dx.doi.org/10.1016/j.apradiso.2016.11.004
N2  - A well-defined neutron spectrum is essential for many types of experimental topics and is also important for both calibration and testing of spectrometric and dosimetric detectors. Provided it is well described, such a spectrum can also be employed as a reference neutron field that is suitable for validating selected cross sections. The present paper aims to compare calculations and measurements of such a well-defined spectra in geometrically similar cores of the LR-0 reactor with fuel containing slightly different enrichments (2 %, 3.3% and 3.6 %). The common feature to all cores is a centrally located dry channel which can be used for the insertion of studied materials. The calculation of neutron and gamma spectra was realized with the MCNP6 code using ENDF/B-VII.0, JEFF-3.1, JENDL-3.3, ROSFOND-2010 and CENDL-3.1 nuclear data libraries. Only minor differences in neutron and gamma spectra were found in the comparison of the presented reactor cores with different fuel enrichments. One exception is the gamma spectrum in the higher energy region (above 8 MeV), where more pronounced variations could be observed.
ER  -

KOŠŤÁL, Michal; Zdeněk MATĚJ; František CVACHOVEC; Vojtěch RYPAR; Evžen LOSA; Jiří REJCHRT; Filip MRAVEC a Martin VEŠKRNA. Measurement and calculation of fast neutron and gamma spectra in well defined cores in LR-0 reactor. \textit{Applied Radiation and Isotopes}. Elsevier, 2017, roč.~120, č.~1, s.~45-50. ISSN~0969-8043. Dostupné z: https://doi.org/10.1016/j.apradiso.2016.11.004.

Přehled o publikaci