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.
Other formats:   BibTeX LaTeX RIS
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
Original language English
Type of outcome Article in a journal
Field of Study 10201 Computer sciences, information science, bioinformatics
Country of publisher Netherlands
Confidentiality degree is not subject to a state or trade secret
WWW 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
Changed by Changed by: RNDr. Pavel Šmerk, Ph.D., učo 3880. Changed: 31/5/2022 17:32.
Abstract
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.
PrintDisplayed: 27/4/2024 18:08