Joint iaea ictp workshop on nuclear reaction data for advanced reactor technologies
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Joint IAEA-ICTP Workshop on Nuclear Reaction Data for Advanced Reactor Technologies. Student’s presentation Calculation of correction factors for neutron capture cross section measurements Pham Ngoc Son, Nuclear Research Institute, VAEC, Vietnam. Introduction.

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Joint iaea ictp workshop on nuclear reaction data for advanced reactor technologies
Joint IAEA-ICTP Workshop on Nuclear Reaction Data for Advanced Reactor Technologies

Student’s presentation

Calculation of correction factors for neutron capture cross section measurements

Pham Ngoc Son, Nuclear Research Institute, VAEC, Vietnam


Introduction

  • The average capture cross sections, <a>, at an average neutron spectrum energy can be measured relative to the standard capture cross section of 197Au by activation method:

fc: correction factors


Introduction
Introduction

  • Correction factors must be introduced to take into account:

    • Multi-scattering of neutron in sample

    • Self-shielding effect

    • Resonance capture with neutrons in low energy background region

Monte Carlo

simulation

Exactly estimation of neutron spectrum

(unfolding method)




Computer programs

69.2eV

70.4eV

Th-232


Computer programs2
Computer programs

Unfolding neutron spectrum of 54keV filtered neutron beam at Dalat Reactor


Computer programs3
Computer programs

Unfolding neutron spectrum of 148.3keV filtered neutron beam at Dalat Reactor


Computer programs4
Computer programs

In a neutron activation experiment, the reaction rate will be measured indirectly, by detection of emitted decay gamma rays from the product nucleus:

Can be Measured by using a HPGe Detector

The second term accounts for the effect of neutron in background region.

The first term of the reaction rate accounts for the effect of neutrons in the primary region of spectrum.


Experimental results
Experimental results

Results of measured capture cross section for some nuclei



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