Isotopic characterization and thermal neutron flux determination of a PuBe neutron source

2017 ◽  
Vol 125 ◽  
pp. 144-149 ◽  
Author(s):  
Ravi Ankit Purty ◽  
Akanchha ◽  
Shikha Prasad
2021 ◽  
Vol 10 (1) ◽  
pp. 11-20
Author(s):  
Tho Nguyen Thi ◽  
Anh Tran Tuan ◽  
Cuong Trinh Van ◽  
Doanh Ho Van ◽  
Duong Tran Quoc ◽  
...  

The accuracy of elements concentration determination using the k0-standardization method directly depends on irradiation and measurement parameters including Non-1/E epithermal neutron flux distribution shape α (ϕ epi ≈1/E1+α ) , thermal-to-epithermal neutron flux ratio f, efficiency ε, peak area… In the case of the irradiation position at the rotary rack of the Dalat Nuclear Research Reactor (DNRR), the difference of thermal neutron flux between the bottom (3.54x1012 n.cm-2.s-1) and the top (1.93x1012 n.cm-2.s-1) of the 15 cm aluminum container is up to 45%. Therefore, it is necessary to accurately determine above-mentioned parameters in the sample irradiation position. The present paper deals with the determination of the distribution of thermal neutron flux along the sample irradiation container by using 0.1% Au–Al wire activation technique. The thermal neutron flux was then used to calculate the concentration of elements in the Standard Reference Material 2711a and SMELS type III using k0-INAA method at different positions in the container. The obtained results with the neutron flux correction were found to be in good agreement with the certified values. In conclusion, the proposed technique can be applied for activation analyses without sandwiching flux monitors between samples during irradiations.


1989 ◽  
Vol 166 ◽  
Author(s):  
John B. Hayter

ABSTRACTThe Advanced Neutron Source (ANS) is a new user experimental facility planned to be operational at Oak Ridge in the late 1990's. The centerpiece of the ANS will be a steady-state research reactor of unprecedented thermal neutron flux (φth ≍ 9·1019 m−2·s−1) accompanied by extensive and comprehensive equipment and facilities for neutron-based research.


2017 ◽  
Vol 18 (1) ◽  
pp. 1 ◽  
Author(s):  
Edi Trijono Budisantoso ◽  
Syarip Syarip

ABSTRAK ANALISIS RANCANGAN DASAR SISTEM PGNAA MENGGUNAKAN SUMBER NEUTRON DARI BEAMPORT REAKTOR KARTINI. Telah dilakukan perancangan dasar sistem PGNAA menggunakan salahsatu beamport reaktor Kartini sebagai sumber neutron.  Moderator neutron  ditempatkan pada ujung kolom berkas neutron untuk membuat berkas neutron menjadi termal.  Berkas diarahkan menuju ruang sampel PGNAA dengan menggunakan kolimator yang berfungsi sebagai penyaring berkas neutron sejajar. Pada penggal kolimator yang berpotongan dengan jendela beamport dipasang neutron beam shutter untuk menutup berkas neutron apabila tidak digunakan untuk PGNAA.  Beam stopper dipasang dibelakang ruang sampel PGNAA untuk menangkap berkas neutron yang  lolos. Perhitungan sifat neutronik dilakukan untuk memilih bahan material yang memenuhi syarat fungsi sebagai sub-komponen PGNAA dan menentukan ukuran geometrinya.  Dari hasil perhitungan diperoleh  data bahan yang baik untuk moderator yaitu grafit, bahan kolimator adalah aluminium, bahan beam shutter dan beam stopper adalah komposit boraks-parafin.  Panjang moderator 90 cm, panjang kolimator 173 cm dengan  tetapan kolimasi D/L=0,015, tebal beam shutter dan beam stopper masing-masing 22 cm dan 30 cm.  Dipasang perisai gamma dan perisai neutron untuk menutup berkas neutron keluar dari sela dinding dalam beamport dan didnding luar kolimator. Bahan perisai tersebut dibuat dari komposit boraks parafin 25% berat dan timbal yang masing-masing panjangnya 50 cm dan 30 cm.  Hasil analisis menunjukkan bahwa dari fluks neutron awal pada beamport bagian dalam sebesar 1,5.1012 n/cm2s dapat menghasilkan fluks neutron termal di ruang sampel PGNAA 1,76.108 n/cm2s dengan arus neutron termal 9,29.108 n/s. Nilai fluks neutron termal tersebut memenuhi persyaratan untuk suatu sistem PGNAA yaitu berada pada orde 106 s/d 108 n/cm2s. Kata Kunci : PGNAA, rancangan dasar, prompt-gamma, analisis aktivasi, neutron-termal, beamport reaktor ABSTRACT BASIC DESIGN ANALYSIS OF PGNAA SYSTEM USING NEUTRON SOURCE FROM BEAMPORT OF KARTINI REACTOR. A basic design of PGNAA system using one of reactor beamports of Kartini reactor as a neutron source have been carried out. Neutron moderator is placed at the inner end of beamport column to make thermal neutron beam. A neutron beam directed  to PGNAA counting chamber by using collimator as a filter to make parallel neutron beam.   At  the midle  of collimator intersect with beamport window, neutron beam shutter is mounted to close when not in use for PGNAA.  Beam stopper mounted behind the sample chamber of PGNAA to capture neutron beam that passes from the sample chamber.  Calculation of neutronic properties of materials was done to choose the material that meet the functional requirements of PGNAA and to determine the geometry size.  Based on the calculational results obtained that good material for moderator is graphite, aluminum as beam collimator, and beam shutter or stopper is made from borax-paraffin composite. The moderator length is 90 cm and collimator length  is 173 cm  with collimation constant D / L = 0,015.  Beam shutter and beam stopper thickness are 22 cm and 30 cm respectively. Gamma and neutron shield are  added  surrounding beam colimator to shield  the radiation out from the pitch between collimator and beamport wall.  The shield material made from composite of parrafin 25 w % borax, and lead with the length of 50 cm and 30 cm respectively.   The analysis result shows that from the neutron flux of 1,5.1012 n/cm2s at the inner side of beamport, can generate thermal neutron flux at the PGNAA sample chamber of 1,76.108 n/cm2s with the thermal neutron current of 9,29.108 n/s. This thermal neutron flux meet the requirement for a PGNAA system i.e. in the order of 106 to 108 n/cm2s.   Keywords : PGNAA, basic design, prompt-gamma, activation analysis, thermal neutron, reactor beamport


1999 ◽  
Vol 26 (1) ◽  
pp. 83-86 ◽  
Author(s):  
R. Schmidt ◽  
R. L. Maughan ◽  
M. Yudelev ◽  
C. Kota ◽  
S. Wanwilairat

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