J 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.

Základní údaje

Originální název

The methodology for validation of cross sections in quasi monoenergetic neutron field

Autoři

MATĚJ, Zdeněk (203 Česká republika, garant, domácí), Michal KOŠŤÁL, Mitja MAJERLE, Martin ANSORGE, Evžen LOSA, Marek ZMEŠKAL, Martin SCHULC, Jan ŠIMON, Milan ŠTEFÁNIK, Jan NOVÁK, Daniil KOLIADKO, František CVACHOVEC (203 Česká republika), Filip MRAVEC (203 Česká republika, domácí), Václav PŘENOSIL (203 Česká republika, domácí), Václav ZACH, Tomáš CZAKOJ, Vojtěch RYPAR a Roberto CAPOTE

Vydání

NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION A-ACCELERATORS SPECTROMETERS DETECTORS AND ASSOCIATED EQUIPMENT, NETHERLANDS, ELSEVIER, 2022, 0168-9002

Další údaje

Jazyk

angličtina

Typ výsledku

Článek v odborném periodiku

Obor

10300 1.3 Physical sciences

Stát vydavatele

Nizozemské království

Utajení

není předmětem státního či obchodního tajemství

Odkazy

Impakt faktor

Impact factor: 1.400

Kód RIV

RIV/00216224:14330/22:00128970

Organizační jednotka

Fakulta informatiky

UT WoS

000856943900001

Klíčová slova anglicky

IRDFF II; Cross section validation; 7Li(p n) neutrons; MCNPX
Změněno: 5. 4. 2023 04:36, RNDr. Pavel Šmerk, Ph.D.

Anotace

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.