Benchmarking Fast Neutrons Leakage Spectrum From Copper Block With 252Cf Source in Center

Author:

Czakoj Tomáš1,Košťál Michal1,Schulc Martin1,Rypar Vojtěch1,Novák Evžen1,Losa Evžen1

Affiliation:

1. Research Center Rez , Hlavní 130, Husinec 250 68, Řež, Czech Republic

Abstract

Abstract Copper is an important material for the nuclear industry; therefore, the correct copper cross section are essential. This paper deals with benchmarking the fast neutron leakage spectrum from a copper block with an intense 252Cf source. The spectrum was measured by the proton recoil method using a stilbene scintillator and spectrometer with pulse shape discrimination. The room effect was subtracted experimentally by shielding cone and confirmed computationally. Simulations were performed using the MCNP6.2 Monte Carlo code. A detailed study on uncertainties has been made. Consequently, as the main source of uncertainties, the measurement apparatus was determined (namely, calibration and number of iterations—up to 15%). From the parameter uncertainty, the most important effects are connected with the mass of cube material—the thickness of the assembly (up to 2%). The effect of copper density uncertainty is low because density was determined experimentally with low uncertainty. The uncertainty related to parameter uncertainties in source structural components is negligible because even neglection of all components leads to a shift in leakage spectra below 7%. Several copper nuclear data libraries were tested as well, and it was found that the calculation with JEFF-3.3 gives the most discrepant results with a discrepancy of up to 60%. The closest results were obtained with ENDF/B-VIII.0 (below 5 MeV, discrepancy within 10%) and JENDL-4.0 (above 5 MeV, discrepancy within 15%). ENDF/B-VII.1 library is relatively close in the region above 5 MeV (discrepancy within 15%), below 5 MeV the agreement is worse (up to 40% discrepancy).

Funder

Ministerstvo Školství, Mládeže a Telovýchovy

Ministerstvo Vnitra Ceské Republiky

Publisher

ASME International

Subject

Nuclear Energy and Engineering,Radiation

Reference16 articles.

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3. Development of Thick Copper Claddings on SS316 L Steel for in-Vessel Components of Fusion Reactors and Copper-Cast Iron Canisters;Fusion Eng. Des.,2018

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5. Copper Neutron Transport libraries validation by Means of a 252Cf Standard Neutron Source;Nucl. Eng. Technol.,2021

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