Nuclear Science and Technology - Volume 8, Number 4, December 2018
Reactivity induced transient analysis when the occurrence
of leakage in the dry irradiation channels
of the Dalat Nuclear Research Reactor
Dau Duc Tu, Nguyen Minh Tuan, Le Vinh Vinh, Huynh Ton Nghiem,
Nguyen Kien Cuong, Tran Quoc Duong, Bui Phuong Nam
Reactor Center, Dalat Nuclear Research Institute, VINATOM
01 Nguyen Tu Luc Str., Dalat, Lamdong, Vietnam.
E-mail: tudd.re@dnri.vn
(Received 06 December 2018, accepted 28 December 2018)
Abstract: The leakage from the reactor pool back into the dry irradiation channels due to corrosion or
mechanics based reason is a postulated event that could occur under operating conditions of the Dalat
nuclear research reactor (DNRR), especially the channel 7-1 which has been installed more than 30
years. When it occurs, the air space in these channels will be occupied by the water, subsequently a
water column will appear in fuel region. The appearance of water column considerably enhances
medium of neutron moderation for its surrounding fuel assemblies. As a result, a positive reactivity is
inserted in the core and this event is classified as an insertion of excess reactivity. This event needs to
be addressed by analysis and assessment from safety point of view and the results of analysis are also
important for updating the reactor operating procedures. This paper presents assumptions, computer
models and the results of analysis for such event in the DNRR by using MCNP5 code (code for
neutronics analysis) and EUREKA-2/RR code (code for transient analysis). The calculation results
include value of reactivity insertion, change in power of reactor, as well as surface temperature of the
hottest fuel assembly. This research contributes to updating the reactor operating procedure.
Keywords: Dalat nuclear research reactor (DNRR), MCNP5, EUREKA-2/RR, reactivity
insertion, transient analysis.
I. INTRODUCTION
A. General information
The Dalat reactor, which is a swimming
pool type reactor and uses light water as
moderator and coolant, has 500 kW thermal
power and put into operation in March, 1984. It
was reconstructed and upgraded from the USA
made 250 kW TRIGA reactor. A number of
structures from the original TRIGA reactor such
as the aluminum tank with the surrounding
concrete shield, four beam-ports, thermal
column and the graphite reflector were
remained.
The reactor core is currently loaded 92
low enriched fuel (LEU) assemblies (19.75%),
3 irradiation channels (2 dry channels and 1
wet channel), 12 beryllium rods and a neutron
trap [1]. The fuel assemblies are VVR-M2
tubular fuel assemblies designed
and manufactured in Russia. Each fuel
assembly consists of three coaxial annular
tubes as well as a header and a tail. The
outermost fuel element has a hexagonal shape
of 32 mm in width across parallel sides and the
other two inner ones have a circular shape of
22 mm and 11 mm in outer diameter,
respectively. The beryllium rods of the reactor
have a hexagonal shape of 32 mm in width
across its parallel sides [1].
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obaric interference caused by Rb on the determination of strontium isotope ratio. However, the small amount of calcium remained in sample solution at this stage was also considered when using cation chromatography technique for removal of Rb interference. The mixed solution containing 1.5 ppm Ca, 0.5 ppm Sr and 0.25 ppm Rb was loaded on the cation exchanger column. The elution was carried out under the same condition as above mentioned. The elution curve is shown in Fig. 7. Fig.7 Elution curves of Rb, Ca and Sr under gradient conditions STUDY ON THE REMOVAL OF INTERFERENCES FOR THE DETERMINATION OF 87 Sr/ 86 Sr 40 The elution peaks from Fig.7 depict that almost Ca presented in mixed solution was eluted together with Sr meanwhile Rb was completely removed within the first 7 eluted fractions. It confirms that the small amount of Ca in sample solution does not interfere with the quantitative separation of Rb, and that the isobaric effect caused by Rb can be completely removed. C. Validation of separation procedure The recovery of strontium through separation procedure was studied by using Sr isotopic standard solutions, in which total concentration of strontium was fixed as 100 μg/L but the isotope ratio 86Sr/87Sr was various with the addition of a certain amount of 86 Sr isotope standard solution in to the natural Sr standard solution (see Table II) in a matrix (100 mg/L Ca and 50 μg/L Rb). The separation procedure was repeated for all synthesized samples under the same conditions as reported above. The results were given in Table II. Table II. Recovery of Sr in synthesized samples Total Sr (µg/L) Spiked 86 Sr (µg/L) 86 Sr/ 87 Sr (by theory) 87 Sr found (µg/L) Total Sr found (µg/L) Recovery (%) 100 0 1.40857 7.80047 103.605 103.61 90 10 2.98187 6.35607 90.801 100.89 80 20 4.90220 5.72470 81.781 102.22 60 40 10.4921 4.40357 62.908 104.85 40 60 21.9123 2.92630 41.804 104.51 The data in Table II show that the recovery of strontium for whole cases (from 100.89% to 104.85%) seemed reliable for Sr analysis through the long procedure of mutual separation. It is thus suitable for the application of Sr isotopic ratio analysis in petroleum drill- holes water samples. The accuracy of separation method was studied by the use of NIST SRM 987 (SrCO3) isotopic standard reference material. The isotopic standard solution was prepared by dissolving a certain amount of standard reference material in dilute HNO3 and a small portion of this solution containing 100 μg/L (as total Sr concentration) was loaded on anion exchanger column. Whole separation procedure was carried out for this standard sample and the final elution fractions were collected for the determination of 87 Sr/ 86 Sr isotopic ratio on ICP-MS. Five replicates of experiment were done and the results were given in Table III. Table III. Analysis of the standard sample SRM 987 87 Sr/ 86 Sr certified value 87 Sr/ 86 Sr analyzed value Absolute Error (%) 0,71034 ± 0.00026 0.71453 ± 0.00836 + 0.59 The relative correctness of analyzed value is 99.41% to that of the certified value for NIST SRM 987, which seems reasonable in NGUYEN THI KIM DUNG, THAI THI THU THUY 41 this study due to the contribution of signal measurement deviation of instrument to the error. That is also the reason why the more precision of the isotopic analysis can be obtained from MC-ICPMS [1]. D. Analysis of petroleum drill-holes water samples Petroleum drill-holes water samples were pretreated to remove the oil and suspended solid particles as denoted in procedure. The chemical composition of sample was analyzed using ICP-MS in order to preliminary classification of the solution matrix. The sample solution was diluted with pure water as needed before applying the separation procedure, followed by the isotopic ratio measurement on ICP-MS. The analytical data were given in Table IV together with total concentrations of Rb and Sr and relative standard deviation (RSD) of 87 Sr/ 86 Sr isotopic ratio measurement. Table IV. Analysis of petroleum drill-holes water samples Sample Code Total Rb (µg/L) Total Sr (µg/L) 87 Sr/ 86 Sr Isotopic ratio Value RSD (%) EW02 36.6 989.8 0.70715 1.17 EW05 45.3 3502.5 0.70734 2.78 EW17 34.5 1240.1 0.70699 1.52 PW03 80.0 824.0 0.70686 1.45 PW04 60.2 423.5 0.70639 1.63 PW14 120.0 1980.0 0.70674 2.46 Analytical results showed that, 87 Sr/86Sr isotopic ratio of petroleum drill-holes water samples was various with different sample matrix. These data relatively agreed with those, which were obtained from similar study [4] of drill-holes water in Vietnam Petroleum Institute, where the water samples were pretreated and the analysis of 87 Sr/ 86 Sr isotopic was carried out by TIMS in over-sea laboratory. IV. CONCLUSIONS The removal of calcium in matrix from petroleum drill-holes water samples and the elimination of rubidium isobaric interference with strontium isotopic ratio determination were successfully achieved by using ion exchange chromatography. The anion exchange resin (Bio-Rad AG1X8 200-400 mesh) was employed for the separation of major calcium by 0.25 M HNO3 in 95% methanol with Sr recovery over 99%. The mutual separation of rubidium and strontium by gradient conditions of HNO3 concentration and flow rate on cation exchanger (Bio-Rad AG50X8 200-400 mesh) was taken part with nearly complete Sr recovery. The validation of method was also studied using isotopic standard solution and standard reference material with relative correctness of the analyzed value about 99.41% to the certified value of NIST SRM 987 reference material. The analytical procedure was then applied for the determination of 87 Sr/86Sr isotopic ratio in STUDY ON THE REMOVAL OF INTERFERENCES FOR THE DETERMINATION OF 87 Sr/ 86 Sr 42 petroleum drill-holes water samples using ICP- MS, which would contribute to the development of an analytical method to supply the demand of petroleum research and exploitation in Vietnam. ACKNOWLEDGEMENT The authors are thankful to the assistance of M.Sc. Ngo Quang Huy on carrying out some preliminary experiments. The financial support under framework of a VINATOM project encoded DTCB.09/18/VCNXH was highly appreciated. REFERENCES [1]. 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Lulić, “Separation of Strontium from Calcium by means of Anion Exchanger and Alcoholic solution of Nitric acid”, J. Radioanal. & Nucl. Chem., Vol.182, No2, 401- 410, 1994. [18]. M.V. Zoriy, A. Rashad, C. Pickhardt, H.T. Mohsen, H. Foerstel, A.I. Helal, N.F. Zahran, and J.S. Becker, “Routine method for 87Sr/86Sr isotope ratio measurement in biological and geological samples after matrix separation by ICP-MS”, Atomic Spectroscopy, Vol. 24(6), pp. 195-199, 2003. INSTRUCTIONS FOR AUTHORS GENERAL INFORMATION Nuclear Science and Technology (NST), an international journal of the Vietnam Atomic Energy Society (VAES) and Vietnam Atomic Energy Institute (VINATOM), quarterly publishes articles related to theory and application of nuclear science and technology. All papers and technical notes will be refereed. It is understood that the paper has been neither published nor currently submitted for publication elsewhere. The copyright of all published papers and notes will be transferred in VAES. 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