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.

Basic information

Original name

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

Authors

KOŠŤÁL, Michal (203 Czech Republic, guarantor), Zdeněk MATĚJ (203 Czech Republic, belonging to the institution), František CVACHOVEC (203 Czech Republic), Vojtěch RYPAR (203 Czech Republic), Evžen LOSA (203 Czech Republic), Jiří REJCHRT (203 Czech Republic), Filip MRAVEC (203 Czech Republic, belonging to the institution) and Martin VEŠKRNA (203 Czech Republic, belonging to the institution)

Edition

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

Other information

Language

English

Type of outcome

Článek v odborném periodiku

Field of Study

10201 Computer sciences, information science, bioinformatics

Country of publisher

Netherlands

Confidentiality degree

není předmětem státního či obchodního tajemství

References:

URL

Impact factor

Impact factor: 1.123

RIV identification code

RIV/00216224:14330/17:00095937

Organization unit

Faculty of Informatics

DOI

http://dx.doi.org/10.1016/j.apradiso.2016.11.004

UT WoS

000392044700008

Keywords in English

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.

Abstract

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 and 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, vol. 120, No 1, p. 45-50. ISSN 0969-8043. Available from: https://dx.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 = {http://dx.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 and 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, vol.~120, No~1, p.~45-50. ISSN~0969-8043. Available from: https://dx.doi.org/10.1016/j.apradiso.2016.11.004.

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