Gamma spectrometer XENON for space gamma burst study on board ISS

1998 ◽  
Author(s):  
Sergey E. Ulin ◽  
K. F. Vlasik ◽  
A. M. Galper ◽  
V. M. Grachev ◽  
Valery V. Dmitrenko ◽  
...  
Keyword(s):  
Gamma Spectrometer ◽  
Gamma Burst

A compact NaI(Tl) with avalanche photodiode gamma spectrometer for in situ radioactivity measurements in marine environment

2021 ◽  
Vol 92 (3) ◽  
pp. 033301
Author(s):  
Zhenyu Sun ◽  
Fan Zhou ◽  
Zhe Cao ◽  
Ziheng Zhou ◽  
Xiaohu Wang ◽  
...  
Keyword(s):  
Marine Environment ◽  
Avalanche Photodiode ◽  
Gamma Spectrometer ◽  
Radioactivity Measurements

Tests of the space gamma spectrometer prototype at the JINR experimental facility with different types of neutron generators

2017 ◽  
Vol 14 (4) ◽  
pp. 591-601
Author(s):  
M. L. Litvak ◽  
A. A. Vostrukhin ◽  
D. V. Golovin ◽  
P. V. Dubasov ◽  
A. O. Zontikov ◽  
...  
Keyword(s):  
Experimental Facility ◽  
Gamma Spectrometer ◽  
Different Types ◽  
Neutron Generators

Method of Non-Destructive Measurement of Natural Radionuclides Concentration in Building Materials

ANRI ◽  
2021 ◽  
Vol 0 (1) ◽  
pp. 31-44
Author(s):  
Aleksey Vasil'ev ◽  
Aleksey Ekidin ◽  
Mariya Pyshkina ◽  
Georgiy Malinovskiy ◽  
Aleksandra Onischenko ◽  
...  
Keyword(s):  
Gamma Radiation ◽  
Flux Density ◽  
Building Materials ◽  
Specific Activity ◽  
Natural Radionuclides ◽  
Gamma Spectrometer ◽  
Average Activity ◽  
Destructive Measurement ◽  
Non Destructive ◽  
Calculated Flux

A method for non-destructive monitoring of the content of natural radionuclides in building materials has been developed. Spectrum measurements of gamma radiation are carried out with a pre-calibrated field gamma spectrometer. The calculation of the average specific activity of natural radionuclides in building materials is carried out by comparing the calculated flux density of unscattered gamma quanta normalized to the specific activity, and the experimentally measured count rates in the photopeak. calculated for the geometry of the room under study and the location of the detector. Application of the developed method makes it possible to estimate the average activity of natural radionuclides in building materials without destruction.

An on-Line Automated Gamma Spectrometer for Coolant Monitoring at the Loss of Fluid Test Facility (LOFT)

1983 ◽  
Vol 30 (1) ◽  
pp. 815-819 ◽  
Author(s):  
J. K. Hartwell ◽  
E. W. Killian ◽  
E. B. Shingleton ◽  
E. E. Owen ◽  
L. O. Johnson ◽  
...  
Keyword(s):  
Test Facility ◽  
Gamma Spectrometer ◽  
On Line ◽  
Fluid Test

Gamma spectrometer systems employing an anti-compton annulus

1966 ◽  
Vol 39 (2) ◽  
pp. 194-216 ◽  
Author(s):  
J. Kantele ◽  
O.J. Marttila ◽  
J. Hattula
Keyword(s):  
Gamma Spectrometer

scholarly journals PEMBUATAN RADIONUKLIDA MOLIBDENUM-99 (99Mo) HASIL AKTIVASI NEUTRON DARI MOLIBDENUM ALAM UNTUK MEMPEROLEH TEKNESIUM-99m (99mTc)

2016 ◽  
Vol 22 (2) ◽  
Author(s):  
Indra Saptiama ◽  
Herlina Herlina ◽  
Sriyono Sriyono ◽  
E. Sarmini ◽  
Abidin Abidin ◽  
...  
Keyword(s):  
Fission Product ◽  
Specific Activity ◽  
Target Material ◽  
Gamma Spectrometer ◽  
Quartz Ampule ◽  
Radionuclide Separation ◽  
Outer Capsule ◽  
Parent Radionuclide ◽  
Daughter Radionuclide ◽  
Uranium Fission

PEMBUATAN RADIONUKLIDA MOLIBDENUM-99 (99Mo) HASIL AKTIVASI NEUTRON DARI MOLIBDENUM ALAM UNTUK MEMPEROLEH TEKNESIUM-99m (99mTc). Pembatasan penggunaan uranium sebagai target untuk produksi 99mTc menyebabkan rumah sakit di Indonesia  kesulitan mendapatkan pasokan 99mTc. Saat ini 99mTc diperoleh dari 99Mo hasil fisi (pembelahan uranium).  Pembuatan radionuklida 99Mo dari aktivasi neutron  molibdenum alam (MoO3) di teras reaktor G.A Siwabessy digunakan sebagai metode alternatif untuk memperoleh 99mTc. Tujuan penelitian ini adalah untuk melakukan pembuatan radionuklida 99Mo dari aktivasi neutron molibdenum alam untuk memperoleh 99mTc. Serbuk MoO3 alam sebanyak 5 gram dikemas dalam ampul kuarsa dan dimasukkan ke dalam inner capsul selanjutnya dikemas menggunakan outer capsul sebagai bahan target. Bahan target diiradiasi di reaktor G.A Siwabessy selama 100 jam. Hasil perhitungan diperoleh aktivitas  99Mo sebesar 65 % dari nilai maksimum yang dapat diperoleh. MoO3 paska iradiasi dilarutkan dengan NaOH 4 M sehingga diperoleh larutan natrium molibdat (Na2MoO4). Radionuklida 99Mo dan 99mTc diukur menggunakan spektrometer gamma. Radionuklida 99Mo terdeteksi dalam produk larutan  Na2MoO4 dengan  aktivitas jenis 99Mo yang diperoleh sebesar 0,81 Ci 99Mo/g Mo.  Radionuklida anak luruh 99mTc dipisahkan dari radionuklida induk 99Mo menggunakan kolom pemisah yang berisi material berbasis zirkonium (MBZ) sebagai penyerap 99Mo. Radionuklida 99mTc hasil pemisahan diperoleh dalam bentuk natrium pertehnetat (Na99mTcO4).dengan recovery yang masih rendah yaitu sekitar 52 hingga 71 %.Kata kunci: Molibdenum, teknesium, radionuklida, pemisahan, iradiasi. PRODUCTION OF ACTIVATED  NEUTRON MOLYBDENUM-99 (99Mo) RADIONUCLIDE FROM NATURAL MOLYBDENUM TO OBTAIN TECHNETIUM-99m (99mTc).  Uranium usage restriction causes the hospitals in indonesia difficult to obtain the suply of  99mTc. At Present, 99mTc is obtanied from molybdenum as a uranium fission product. Production of 99Mo radionuclide resulted from neutron activated natural molybdenum (MoO3) in G.A Siwabessy reactor could be used  as a alternatif method for producing 99mTc. The aim of this research is synthesize of   99Mo radionuclide from neutron activated natural molybdenum  (MoO3) to obtain 99mTc. The five grams of  MoO3 powder was packed in a quartz ampule and inserted into inner capsule then also inserted into outer capsule as a target material. It was iradiated in G.A Siwabessy reactor for 100hours. Based on theoritical calculation, about 65 % of maximum 99Mo activity could be recovered. After Irradiation,  MoO3 was dissolved by NaOH 4 M solution so it was natrium molybdate (Na2MoO4) solution. 99Mo and 99mTc radionuclide were analyzed using gamma spectrometer. 99Mo radionuclide was detected on Na2MoO4 solution as product that had specific activity of 0.81 Ci 99Mo/ g Mo. 99mTc as daughter radionuclide was separated from 99Mo as parent radionuclide using separated column containing zirconium based material (ZBM) as 99Mo adsobent. 99mTc radionuclide has been succesfully separated using ZBM column although recovery of 99mTc  was quite low in which approximately 52 to 71 %. The 99mTc radionuclide was recovered in the form of sodium pertechnetate (NaTcO4) solution.Keywords: Molybdenum, technetium, radionuclide, separation, irradiation.

scholarly journals PORTABLE GAMMA SPECTROMETER FOR SAFEGUARDS USE.

1967 ◽  
Author(s):  
E.M. Sheen ◽  
J.I. Forsberg ◽  
C.A. Ratcliffe
Keyword(s):  
Gamma Spectrometer
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