Determination of fuel burnup distribution of a research reactor based on measurements at subcritical conditions

The k0-based neutron activation analysis (k0-NAA) has been applied for determination of trace multi-element in 5 fruits: Orange, tomato, persimmon, pear and apple. The samples were collected in Vietnam and Korea, and dried-frozen in laboratory at a temperature of -650C, weighed approximately 50 mg or 100 mg each sample, and put in clean polyethylene bags for short and long time irradiations, respectively. The NIST-1547 (Peach Leaves) and IAEA-V-10 (Hay Powder) were used for the purpose of quality control. Both analytical and standard samples were irradiated in the 500 kW Dalat research reactor (Vietnam) and the 20 MW HANARO research reactor (Korea). Concentration of 16 elements: Al, As, Au, Br, Ca, Cl, Co, Eu, Fe, K, La, Mg, Mn, Na, Rb and Zn were determined. By comparison the concentrations of trace elements in the investigated Vietnam and Korea’s fruits, revealed that they are mostly similar between two places. However, the Ca concentration in orange from Vietnam was approximately 2.5 times higher than that one from Korea, whereas the Ca concentration in pear from Vietnam was approximately 21 times lower than that one from Korea. The Mn concentrations in all of fruits that collected in Vietnam were mostly higher than those collected in Korea, ranging between 1.4 to 2.2 times.

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Determination of the Iodine Content of Some Commonly Consumed Foods in Zaria Metropolis, Nigeria, Using PCNAA and Sandell-Kolthoff Reaction

Journal of Nuclear Chemistry ◽

10.1155/2014/780640 ◽

2014 ◽

Vol 2014 ◽

pp. 1-4

Author(s):

T. Muhammad ◽

A. Uzairu ◽

M. S. Sallau ◽

M. O. A. Oladipo

Keyword(s):

Neutron Activation Analysis ◽

Standard Deviation ◽

Test Score ◽

Research Reactor ◽

Iodine Content ◽

Food Samples ◽

Average Percentage ◽

Average Percentage Deviation ◽

Percentage Standard Deviation

The Nigerian Research Reactor-1 was employed in the analysis of iodine in local food samples at an operating flux of 5.0×1011 ncm−2 s−1. Preconcentration neutron activation analysis (PCNAA) was compared against the most common spectroscopic (Sandell-Kolthoff reaction) technique, giving a concentration range of 0.295 to 2.960 mg/Kg and 0.264 to 2.725 mg/Kg, respectively, with an average percentage deviation of 11.34% and a positive correlation between the methods at 0.89. PCNAA and Sandell-Kolthoff spectroscopy of NIST 1548a reported values of 0.759±0.06 mg/Kg and 0.751±0.05 with Student’s t-test score of 1 and 0.95 and percentage standard deviation of 0 and 1.12%, respectively.

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Combination and optimization of the cyclic NAA modes at the Dalat research reactor for determination of selenium in biological materials using 77mSe

Journal of Radioanalytical and Nuclear Chemistry ◽

10.1007/s10967-016-4784-7 ◽

2016 ◽

Vol 309 (1) ◽

pp. 185-188 ◽

Cited By ~ 1

Author(s):

Van Doanh Ho ◽

Manh Dung Ho ◽

Quang Thien Tran ◽

Thi Sy Nguyen ◽

Nhi Dien Nguyen

Keyword(s):

Research Reactor ◽

Biological Materials ◽

Dalat Research Reactor

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RTS - 1 - Galilei Decommissioning Project

9th ASME International Conference on Radioactive Waste Management and Environmental Remediation: Volumes 1, 2, and 3 ◽

10.1115/icem2003-4661 ◽

2003 ◽

Author(s):

A. Boschi ◽

E. Cimini ◽

F. Pagni ◽

L. Parracone ◽

M. Pocai ◽

...

Keyword(s):

Research Reactor ◽

Thermal Flux ◽

Spent Fuel ◽

Radiological Risk ◽

Radioactive Materials ◽

Thermal Output ◽

Protective Custody ◽

First Time ◽

Waste Characterisation

The RTS-1 “Galileo Galilei” is an open pool research reactor light water moderated and cooled. It had a maximum thermal output of 5 MWth and an average thermal flux of 5 E+13 n/cm2sec. It became critical for the first time on April 1963 and it was definitely shutdown in March 1980. The reactor is situated at CISAM (Joint Centre of Studies and Military Application - Italian Ministry of Defence), S. Piero a Grado, Pisa, Italy, and its decommissioning is in progress. In this paper the strategy adopted to achieve the green status of the reactor site is discussed, with particular attention on the different steps to be done according to the national laws. Emphasis is placed on the characteristics of two different conditions required, namely Passive Protective Custody, which is a step necessary to allow the decay of the radioactive materials present into the plant to decrease the radiological risk to operate safely, and Unconditioned Release, in which all the materials can be released without radiological restrictions. Another aspect discussed in this paper is the effort spent on the determination of the radioisotopic abundance of the reactor components, the personal dose evaluation due to the necessary activities to achieve two different status of “Passive Protective Custody” and “Unconditioned Release” and the waste characterisation. The necessary authorisations to start decommissioning has been obtained as far as concern the removal of spent fuel and the dismantling of some experimental equipments.

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Analysis of the reactivity coefficients and fuel burnup for MNSR research reactor using DRAGON5/DONJON5 codes

Radiation Physics and Chemistry ◽

10.1016/j.radphyschem.2019.03.006 ◽

2019 ◽

Vol 160 ◽

pp. 56-62

Author(s):

Jamal Al Zain ◽

O. El Hajjaji ◽

T. El Bardouni ◽

Afaf El Mtili

Keyword(s):

Research Reactor ◽

Fuel Burnup ◽

Reactivity Coefficients

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Determination of backscattered neutrons/gammas from open beam port of a research reactor

EPJ Web of Conferences ◽

10.1051/epjconf/202022504032 ◽

2020 ◽

Vol 225 ◽

pp. 04032

Author(s):

Anže Jazbec ◽

Bor Kos ◽

Vladimir Radulović ◽

Klemen Ambrožič ◽

Luka Snoj

Keyword(s):

Research Reactor ◽

Gamma Dose ◽

Computation Model ◽

Beam Tube ◽

Horizontal Beam ◽

Beam Port ◽

Jozef Stefan Institute ◽

Stefan Institute ◽

Triga Mark Ii

Neutron and gamma dose rate calculations were carried out around horizontal beam tube no. 5 at the Jožef Stefan Institute (JSI) TRIGA Mark II research reactor. Results were compared to the experimental measurements in order to verify the computation model. In addition, another set of calculations and measurements was carried out, where an additional shield made out of concrete and paraffin was installed. With that configuration, we were able to study neutron and gamma scattering.

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