Measurement of cross sections for flux monitor reactions using quasi-monoenergetic neutrons

被引：2

作者：

Vashi, Vibhuti ^{[1
]}

Makwana, Rajnikant ^{[1
]}

Mukherjee, S. ^{[1
]}

Soni, B. K. ^{[1
]}

Mehta, M. H. ^{[2
]}

Parashari, S. ^{[1
]}

Singh, R. K. ^{[1
]}

Chauhan, R. ^{[1
]}

Suryanarayana, S., V ^{[3
]}

Nayak, B. K. ^{[4
]}

Sharma, S. C. ^{[3
]}

Naik, H. ^{[3
]}

Singh, N. L. ^{[1
]}

Nag, T. N. ^{[4
]}

机构：

[1] Maharaja Sayajirao Univ Baroda, Vadodara 390002, India

[2] Inst Plasma Res, Gandhinagar 382428, Gujarat, India

[3] Bhabha Atom Res Ctr, Nucl Phys Div, Mumbai 400085, Maharashtra, India

[4] Bhabha Atom Res Ctr, Radiochem Div, Mumbai 400085, Maharashtra, India

来源：

EUROPEAN PHYSICAL JOURNAL PLUS | 2021年 / 136卷 / 07期

关键词：

NUCLEAR-DATA; FISSION; TRANSMUTATION; THORIUM;

D O I：

10.1140/epjp/s13360-021-01673-9

中图分类号：

O4 [物理学];

学科分类号：

0702 ;

摘要：

The reaction cross sections of 197Au(n,2n)196Au, 115In(n,n ' )115mIn, 232Th(n,f)97Zr, and 238U(n,f)97Zr reactions were measured at different neutron energies using standard neutron activation analysis (NAA) technique followed by off-line gamma -ray spectrometry. The irradiation was performed using the BARC-TIFR Pelletron facility in Mumbai, India. The quasi-monoenergetic neutron beam was generated using the 7Li(p,n)7Be reaction. The measured data are compared with available experimental data in the EXFOR database, different evaluated libraries such as ENDF/B-VIII.0, JEFF-3.3, JENDL-4.0, CENDL-3.1, IRDFF II, TENDL-2017 and with the results predicted using nuclear modular code TALYS-1.9. The TALYS-1.9 code was used for a better description of the present work and literature data. The reactions studied in the present paper are considered flux monitor reactions as they are widely used for the measurement of neutron flux in NAA-technique.

引用

页数：12

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