Detailed Information on Publication Record
2022
The methodology for validation of cross sections in quasi monoenergetic neutron field
MATĚJ, Zdeněk, Michal KOŠŤÁL, Mitja MAJERLE, Martin ANSORGE, Evžen LOSA et. al.Basic information
Original name
The methodology for validation of cross sections in quasi monoenergetic neutron field
Authors
MATĚJ, Zdeněk (203 Czech Republic, guarantor, belonging to the institution), Michal KOŠŤÁL, Mitja MAJERLE, Martin ANSORGE, Evžen LOSA, Marek ZMEŠKAL, Martin SCHULC, Jan ŠIMON, Milan ŠTEFÁNIK, Jan NOVÁK, Daniil KOLIADKO, František CVACHOVEC (203 Czech Republic), Filip MRAVEC (203 Czech Republic, belonging to the institution), Václav PŘENOSIL (203 Czech Republic, belonging to the institution), Václav ZACH, Tomáš CZAKOJ, Vojtěch RYPAR and Roberto CAPOTE
Edition
NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION A-ACCELERATORS SPECTROMETERS DETECTORS AND ASSOCIATED EQUIPMENT, NETHERLANDS, ELSEVIER, 2022, 0168-9002
Other information
Language
English
Type of outcome
Článek v odborném periodiku
Field of Study
10300 1.3 Physical sciences
Country of publisher
Netherlands
Confidentiality degree
není předmětem státního či obchodního tajemství
References:
Impact factor
Impact factor: 1.400
RIV identification code
RIV/00216224:14330/22:00128970
Organization unit
Faculty of Informatics
UT WoS
000856943900001
Keywords in English
IRDFF II; Cross section validation; 7Li(p n) neutrons; MCNPX
Změněno: 5/4/2023 04:36, RNDr. Pavel Šmerk, Ph.D.
Abstract
V originále
Dosimetry cross sections are fundamental quantities for proper determination of the neutron fluences in points of interest under heavy radiation load. One of the critical applications is the Reactor Pressure Vessel aging management, related to the correct estimation of its residual lifetime or for many non-reactor applications including neutron dosimetry of accelerator-based fields or space applications. The neutron flux of neutrons above 12 MeV in reference to fission spectra is below 1%. Therefore, new reference neutron fields with average energy above 5 MeV should be developed for the validation of neutron dosimetry cross sections up to 60 MeV. This paper presents the testing of a new methodology for the use of quasi monoenergetic neutron fields, where different sensitivity allows validations of the dosimetry cross section at energies much higher than the average energy of around 2 MeV typical of fission spectra. The exact shape of the neutron spectrum in the tested fields is measured by stilbene spectrometry. The total flux is determined from Ni and Al flux monitors. The developed methodology was applied to the validation of selected reactions from the IRDFF-II library showing satisfactory agreement.