Institute Of Nuclear Sciences Research Articles

Ionomic variation characterization in African leafy vegetables for micronutrients using xrf and hplc

Beside the phytochemical, ionomic fingerprinting represents the inorganic trace element composition of the cellular and organismal component. High-throughput elemental analysis technologies, such as X-Ray Fluorescence (XRF), are applied to ionomic analysis whereas phyto-chemical analyses tend to be in vitro. Both could contribute to: (a) insights on ionome-phytochem micronutrient composition; (b) genetic diversity variant discrimination among accessions to allow simple grouping;(c) core and/or reserve collections rationalization; (d) integration of bioinformatic and genetic tools; and (e) micronutrient-dense varietal improvement and/or cropping decisions. First, variant discrimination was appraised on individual element criterion (e.g. K or Ca or Fe or Zn). Second, on a multiple element (K & Ca & Fe & Zn) condition upon which nutrahealth-implied ionomic variant conditions were rationalized as: (a) Core ‘exceptional’ grade collections scored between E8 and E10;(b) Core ‘Medium’ grades (M5-M7); and (c) ‘Least’ exceptional (Ll-L4) scored and regarded as reserve collections. Objectives were to: (1) Investigate a phyotchem background among the selected African Leafy Vegetables (ALVs) for coupling with ionome grading; (2) Assess variation among accessions based on single element criterion; (3) Characterize cumulative nutrahealth-implied ionomic variation among ALVs. Eleven ALV accessions were raised from seed at the University of Nairobi Greenhouse (2006) and leafy parts harvested. XRF was carried out at the Institute ofNuclear Science and Technology, University of Nairobi. High Performance Liquid Chromatographic (HPLC) analyses were done at the Tanzania Food and Nutritional Centre. Highly significant density variation (p< 0.001) among accessions due to Lutein and â-carotene suggested the phytochem effectiveness for variant discrimination accounting for 0.79 and 0.87 of (R2) variation. The single element K discriminator basis was highly significant (p

Comparative performance of semi-absolute k 0-instrumental neutron activation analysis and Inductively Coupled Plasma Optical Emission Spectrometry (ICP-OES) for compositional decoding of aluminum base alloys

Abstract Samples of certified aluminum base alloys were analyzed by semi-absolute, standardless k 0-instrumental neutron activation analysis (k 0-INAA) for compositional decoding. Irradiations were performed at two research reactors located at Pakistan Institute of Nuclear Science and Technology having nominal thermal neutron fluxes of 1013 and 1012 cm−2 s−1. The experimentally optimized parameters for NAA suggest a maximum of three sets of irradiations for the quantification of 8 major and minor elements. Moreover, the same conditions provided quantitative results for 10 other elements as impurities, which were not reported by the supplier of the reference material. The same alloys were analyzed by inductively coupled plasma optical emission spectrometry (ICP-OES) where all impurity elements, quantified by k 0-INAA, were below the detection limits. A comparison of % relative deviation of the results obtained by k 0-INAA and ICP-OES revealed that the former has better accuracy than ICP-OES, but k 0-INAA has poor limits of detection for Mg, Si and Ti in aluminum base alloy.

Calibration of routine dosimeters in radiation processing: Validation procedure for in-plant calibration

The essential prerequisite of radiation dosimetry is to provide quality assurance and documentation that the irradiation procedure has been carried out according to the specification requirement of correct calibration of the chosen dosimetry system. At the Radiation Plant of the Vinca Institute of Nuclear Sciences we compared two recommended protocols of irradiation procedures in the calibration of dosimetry systems in radiation processing: (1) by irradiation of routine dosimeters (ethanol-chlorobenzene - ECB) at the calibration laboratory and (2), by in-plant calibration with alanine transfer - dosimeters. The critical point for in-plant calibration is irradiation geometry, so we carefully positioned the phantom carrying both dosimeters in order to minimize dose gradients across the sample. The analysis of results obtained showed that the difference among determined absorbed doses for the construction of calibration curves between these two methods, (alanine vs. ECB), is less than 1%. The difference in combined standard uncertainty for each calibration procedure is 0.1%. These results demonstrate that our in-plant calibration is as good as calibration by irradiation at the calibration laboratory and validates our placement of the irradiation phantom during irradiation.

Elemental analysis of topaz from northern areas of Pakistan and assessment of induced radioactivity level after neutron irradiation for color induction

To study the impurity elements, which render color-induced topaz long lived radionuclides, three samples of topaz, from three different cities of the Northern Pakistan (Baltistan, Gilgit and Mardan) were analyzed using k 0 instrumental neutron activation analysis (k 0-INAA). The samples were irradiated in Pakistan Research Reactor-1 (PARR-1) and PARR-2 at Pakistan Institute of Nuclear Science & Technology (PINSTECH), Islamabad. The method was validated by analyzing IAEA-S7 reference material. In three samples a total of 22 trace level impurity elements were quantified. Among impurities, 10 elements including As, Ce, Ga, Ge, La, Na, Sb, Sc, U and Zn were common in topaz of all the three places. The storage time has been calculated for each sample required to bring the induced radioactivity down to permissible level given by US National Regulatory Commission.

Mineral micronutrient density characterization using energy dispersive X-Ray Fluorescence (XRF) analysis in four on-farm Kenyan wild African fruit tree germplasm

Kenya has over 400 marginalized indigenous fruit species. A majority found in natural habitats are allegedly high in micronutrients that could help mitigate the prevailing micronutrient nutrahealth deficiencies. Amplifying their nutrahealth value more as nutraceutical than wild species, and coupled with local level communitycentred promotion for use and conservation, could stimulate the uncommon opportunities for decentralized and locale-specific community use and conservation. Thus conservation-by-use could enlarge the nutrahealth security basket as well as mitigate loss of the vanishing fruit species. In retrospect, value-adding nutrahealth research is needed to change the un-informed mind. Thus, the objectives of the study were to: (1) tag Mineral-Referred sites (MRS) influencing Fruit Mineral-Density variation (FMDVAR) among Grewa, Rhus, Boabab and Jackfruit accessions; and (2) apply a nutrametric value (grading) test to classifying FMD variation (FMDVAR) within the realm of nutraceutical food, nutrition and health promise. Fruit portions with their tree trunk adjoining soils were collected in 2003/04 from Kanduyi-Chwele- Nalondo (Bungoma) transect; Maseno-Esivalu (Maseno); and Kaseme- Masongaleni (Kibwezi) and subjected to XRF analysis at the Institute of Nuclear Science and Technology in the University of Nairobi. A Clustered-Bar-Graphing test was used to obtain Ca, K, Fe, Zn, Cu, Mn as variation-picking elements which were turned into MRS X-variables upon which fruit species mineral-density variation was determined. Significant (p < 0.05) FMDVAR x MRS and phyto-region x FMDVAR interactions were detected. Rhus spp had the highest Fe-Mn > Grewa spp > Jackfruit > Ficus > Boabab spp depending on locations they were collected from. In that order, Ficusshowed the highest iron-manganese but had the lowest Zn-Cu. Jackfruit, with Fe-Mn third in line, had highest Zn-Cu. There was no accession with ‘all-winner’ elements. In density terms some minerals were top while others were variably low. High uptakeability of elements in the tree species such as demonstrated by Rhus may be indicative of their soil-mining (a depletion effect) and/or fruit accumulation (a nutra-health plus) tendency. On the overall, nutrametric valuation (NTV) confirmed that Rhus and Ficus had highest fruit micronutrient variation relative to Jackfruit and Boabab. NTV clusters did not show a one-to-one soil-to-plant element matching between plant and soil mineral content. Plant micronutrient patterns show the potential for exploiting the indigenous trees for development of nutrahealth cropping.Key words: XRF, Micronutrient Density, African Fruits

Towards an international authoritative system for coordination and management of a unique recommended k0-NAA database

This paper describes the evolution of the database in k 0-standardized neutron activation analysis ( k 0-NAA), ranging from its full supervision by the founders of the k 0-method at the Institute for Nuclear Sciences (INW)/Gent and the Central Research Institute for Physics (KFKI)/Budapest (from about the mid 1970s up to the early 1990s), to the present situation (roughly speaking starting with the first k 0 Users Workshop in 1992) where an increasing number of researchers from institutes allover the world are reporting on their experimental work aiming at the improvement and extension of the existing database. Although these individual contributions are undoubtedly commendable, the resulting fragmentary data sets leave behind important questions with respect to interpretation, evaluation, integration and recommendation, as illustrated with the (extreme) example of 131Ba. This situation urgently calls for establishing and managing an international authoritative system for the coordination and quality control of a unique database with recommended data for k 0-NAA, considering such parameters as accuracy, traceability and consistency. In the present paper, it is proposed to entrust this task to a standing “Reference k 0-Data Subcommittee” of the k 0-ISC ( k 0 International Scientific Committee).

Repatriation of Vinča RA reactor spent fuel

AbstractThe RA research reactor is located at the Vinca Institute of Nuclear Sciences near Belgrade, Serbia. The reactor is a 6·5 MW, tank-type, heavy water moderated and cooled reactor of Russian design which commenced operation in 1959. After being temporarily shut down in 1984 for refurbishment, a final shutdown decision was made in 2002. Operations are underway to safely remove and repatriate the spent nuclear fuel (SNF) to the Russian Federation (RF), as well as to improve waste management throughout the Vinca site and prepare a plan for reactor decommissioning. As a major activity within the Vinca Institute Nuclear Decommissioning (VIND) Programme, the repatriation of over 8000 SNF elements containing 2·5 tons of uranium metal will significantly reduce nuclear proliferation and environmental safety risks confronting the current facility. Poor water quality in the SNF storage basins and degraded fuel integrity significantly challenge efforts to repackage and transport the SNF. This paper will focus o...

Implementation of the k 0-NAA method by using k 0-IAEA software and the NAA#3 irradiation hole at the HANARO research reactor

This study intended to demonstrate the use of k0-IAEA software with the NAA#3 irradiation hole in the HANARO research reactor and the gamma-ray spectrometers at the NAA laboratory in the Korea Atomic Energy Research Institute (KAERI). NIST SRM 2586-Soil was chosen as a sample to validate the analytical protocol by using the k0-IAEA software. Twenty four elements were determined and the resultant deviations between the experimental results and the certified values were all within 10% except for Dy. In addition, an analysis of three types of synthetic multielement standards (SMELS) prepared by the Institute for Reference Materials and Measurements (IRMM) and Institute of Nuclear Science (INW) in Belgium was executed. The analytical results agreed well with the assigned values and the U-scores for most of the elements were lower than 2.

PET without cyclotron

Positron emission tomography (PET) has been well established noninvasive imaging technique for diagnosis, staging/ restaging and monitoring of therapy response in oncology. Molecular imaging using positron emitting radionuclides kinetics provides quantitative in vivo assessment of biological and physiological processes involved in the earlier stages of disease progression. Because of the short life time (hours) of many of the PET radioisotopes, a cyclotron and radiocompound synthesis facility is required. One of the most widely recognized advantages of PET is the use of the positron emitting biologic radiotracers, e.g., C (T = 20 min), N (T = 10 min), O (T = 2 min), and most important F (T = 110 min) that mimic natural substrate. However, due to relatively short half-lives, they are unable to be transported to sites at great distances from the production facility. The production of radioisotopes using a cyclotron/accelerator demands a knowledge of excitation functions (reaction cross section), development of high current targets, radiochemical separations at no-carrier added level, recovery of enriched target materials in most of the cases, remote control and highly trained manpower for running, repair and maintenance. Cyclotrons are generally used for production of short-lived radioisotopes; however, long-lived isotopes are also produced which can be used at distant places. Fast and high resolution imaging method, such as single photon emission computed tomography (SPECT) is now commonly available for diagnostic studies in developing countries, whereas PET facility is rarely employed for patient management due to non-availability of cyclotron in these countries. Positron emission tomography has two major advantages over SPECT, namely, better spatial resolution and greater sensitivity. The number of positron emitting radionuclides is large. However, most of the PET studies are performed near to cyclotron production facility with short-lived positron emitters (C, O, N, and F). A tabulation of 157 positron emitting radionuclides which have the physical characteristics deemed appropriate for radiopharmaceutical use is provided by Lambrecht [1]. Some cyclotron produced generator radionuclides have also been listed by Qaim [2]. Table 1 presents the generator produced positron emitters, which can be utilized far from production site for PET studies. Production route of parent in a cyclotron and separation of daughter is discussed elsewhere [3]. Antibody-PET imaging might be of value for the selection of radioimmunotherapy (RIT) candidates to confirm tumor targeting and to estimate radiation doses to tumor and normal tissues. One of the requirements to be set for such a scouting procedure is that the biodistributions of the diagnostic and therapeutic radioimmunoconjugates should be similar. The potential of the positron emitters zirconium-89 (Zr) and iodine-124 (I) for this approach, as these radionuclides have a relatively long half-life that matches with the kinetics of MAbs in vivo (T1/2 3.27 and 4.18 days, respectively), were evaluated [4]. Other long-lived positron emitters, which may be used at distant places are, V (T = 16 d), Mn (T = 5.59 days), As (T = 17.78 days), and Au (T = 39.5 h). Through the supply of a long-lived parent radionuclide, from which a short-lived daughter radionuclide can be milked off periodically at hospitals, it has become possible A. Mushtaq (&) Isotope Production Division, Pakistan Institute of Nuclear Science and Technology, P.O. Nilore, Islamabad, Pakistan e-mail: mushtaqa@pinstech.org.pk

Intercomparison of Personal Dosimetry for Service Providers in Pakistan

An intercomparison exercise for personal dosimetry service providers within Pakistan was conducted by the Health Physics Division of the Pakistan Institute of Nuclear Science and Technology. Participation in the exercise was on voluntary basis. The exercise was carried out to harmonize individual dose monitoring techniques for high energy photons in terms of a new operational quantity, namely personal dose equivalent Hp(10), for personal dosimetry in accordance with the recommendations of the International Commission on Radiation Units and Measurements. Each laboratory submitted 25 dosimeters for participation in the intercomparison exercise. Protection level Co and Cs sources were used for irradiation of dosimeters on a water phantom according to International Atomic Energy Agency protocol at the Secondary Standard Dosimetry Laboratory. Hp(10) doses for five different dose levels were measured by the participating laboratories. The ratios of measured dose/true dose (Hm/Ht) remained in the range of 0.66 to 1.11 for the Co source and 0.84 to 1.17 for the Cs source. Performance of service providers' laboratories to measure Hp(10) doses was analyzed and evaluated in terms of trumpet curves plotted for photons at a 95% confidence level.

A channel for modification of materials with post-accelerated or decelerated multiply charged ion beams

At present, heavy ion beams from the electron cyclotron resonance (ECR) ion source in the Laboratory of Physics of the Vinča Institute of Nuclear Sciences, Belgrade, Serbia, are employed in a channel for surface modification of materials. The source and channel were commissioned in 1998, and have been used since that time by a number of user groups from the Vinča Institute and other scientific and educational institutions in Serbia. However, since the maximum extraction voltage of the source is +25 kV, sometimes the extracted beams do not have sufficiently high energies for such applications. Therefore, in order to solve this problem, we have decided to construct a new channel, to be used for deeper modification of materials. The beams obtained from the source will be post-accelerated by biasing the target to be irradiated to the negative potentials of down to −100 kV. For example, we shall be able to bombard the target with the 132Xe 24+ beam of the energy of up to 3 MeV, instead of up to 600 keV, in the case without the biasing system. An additional possibility will be to bias the target to the positive potentials of up to +25 kV and thus decelerate the beams extracted from the source down to the energies of about 1 keV. Consequently, one will be able to modify materials with the beams in a wide energy range, from ∼1 to ∼3 MeV, which is rarely met at similar experimental set-ups. It must be noted that changing the post-accelerated or decelerated beam energy in the new channel will be performed simply by adjusting the power supply of the biasing system, without any adjustments of the source and of the transport elements between the source and the interaction chamber.

Dosimetric characteristics of high sensitive [formula omitted]:Tb solid TL detector

Thermoluminescence dosimetric characteristics of Mg 2 SiO 4 : Tb in form of sintered pellets developed at the Institute of Nuclear Sciences, Vinc`a, Belgrade, are presented. Mg 2 SiO 4 : Tb is a TL material with attractive features for dosimetric applications such as ultra high TL sensitivity, simple glow curve with the main TL peak at about 210 °C and low fading. The dosimetric properties of this TL detector examined in this study include glow curve shape, TL sensitivity, annealing procedure and reproducibility, photon dose response, minimum detectable dose, energy response, fading characteristics, light induced effect and optically stimulated luminescence (OSC) signal.

Exit reactor Thetis/Ghent (1967–2003): A recollection of its significant contribution to NAA and its leading role in the development of the k0-standardization

After 36 years of operation, reactor Thetis at the Institute for Nuclear Sciences (Ghent University) was decommissioned in December 2003. On this occasion, a survey is presented of the characteristics and features of Thetis, which were opening the way to its significant contribution to NAA and its leading role in the development of the k 0-standardization. A summary is given, including a few specific examples, of fundamental analytical developments and practical applications based on irradiations in the reactor Thetis.

Individual monitoring based on magnesium borate

Valuable features of magnesium borate sintered solid thermoluminescence dosemeters (TLDs), such as near tissue- equivalence, high sensitivity, and good performances for X, gamma, beta and neutron dosimetry, were developed and produced by the Institute of Nuclear Sciences, Vinca. These features form the basis for using this type of TLDs successfully for legal personal dosimetry control in Serbia for the past 27 y. The dosimetric properties of this TL material are presented in this study.

Influence of CdS-filler on the thermal properties of poly(methyl methacrylate)

Nowadays, polymer composites are widely used in many fields of technology. Among them a significant roles play polymers containing semiconductor particles, especially for the manufacturing of electronic devices [1]. Therefore, it is important to understand the effects of these fillers on the properties of composites. The properties of composites mostly depend on size and shape of filler particles, their concentration as well as the type of interaction with polymer matrix. Poly(methyl methacrylate) (PMMA) is an important thermoplastic material with excellent transparency. However, its lower thermal stability restrains it from applications in higher temperature region. To improve the thermal properties of PMMA, fillers such as silica, titania, zirconia and alumina [2–8], as well as clay [9] were introduced into the PMMA. Recently, we showed significant improvement of the thermal stability of the polystyrene matrix filled up to a few mass% with the CdS nanoparticles (the mean particle diameter was 50 A) [10]. This effect is a consequence of high surface to bulk ratio of the CdS nanofiller and the presence of large number of dangling bonds that lead to the formation of chemical bonds between surface atoms of the CdS nanoparticles and the polymer chains. However, the synthetic route for preparation of nanocomposites is quite complex involving transfer of nanoparticles from water to organic phase. Because of that, simplified synthetic route for preparation of the polystyrene–CdS composite was developed based on mixing the CdS-filler in micrometer size range with the polymer melt [11]. In the present study, we synthesized new composite using PMMA as a matrix and submicronic CdS particles as a filler. The composite was characterized using structural techniques and the influence of the CdS-filler on the thermal properties of the PMMA–CdS composite was discussed in detail. The CdS-filler particles were prepared by mixing 500 mL of aqueous solutions containing 7.0 · 10 M Cd(NO3)2 (Merck) and 1.0 · 10 M Na2S (Fluka) at 90 C. Precipitate was washed out several times with water. In order to make surface of CdS-filler particles hydrophobic 150 (L of castor oil (Akzo Chemie) was added. Finally, colloidal dispersion was filtered, and precipitate was dried. The PMMA–CdS composite was prepared by dissolving appropriate amount of CdS in solution of PMMA (Diakon CMG314V)) in xylene, and consequent evaporation of solvent. The contents of inorganic phase were chosen to be 1.5, 3.0 and 6.0 wt%. In order to characterize morphology of the PMMA–CdS composite atomic force microscopy (AFM) was performed using Quesant Universal SPM instrument operating in noncontact (intermittent) mode. Measurements were performed in air using Si probes. Typical AFM image of the PMMA–CdS composite is shown in Fig. 1. Non-agglomerated spherical CdS particles in the size range from 0.2 to 0.35 lm in the PMMA matrix can be noticed. The X-ray diffraction (XRD) spectra of the PMMA–CdS composites were obtained by using Philips PW 1710 diffractometer. A typical XRD spectrum of the PMMA–CdS composite is shown in Fig. 2. The XRD peaks corresponding to 1 1 1, 2 2 0 and 3 1 1 crystallographic planes indicate that CdS is in a cubic phase (12] The CdS XRD peaks are very broad due to the small crystalline domains in the particles. The Scherrer diffraction formula was used to estimate the crystalline domain size (D) J. Kuljanin-Jakovljevic AE Z. Stojanovic AE J. M. Nedeljkovic (&) Vinca Institute of Nuclear Sciences, P.O. Box 522, 11001 Belgrade, Serbia and Montenegro e-mail: jovned@vin.bg.ac.yu J Mater Sci (2006) 41:5014–5016 DOI 10.1007/s10853-006-0111-y

Measurement of radionuclides in contaminated environmental matrices: Participation in Quality Assessment Programme (QAP) of U.S. Department of Energy's Environmental Monitoring Laboratory

A Quality Assessment Programme (QAP) was initiated by the U.S. Department of Energy (DOE) in 1998 to establish creditability in the measurements of radionuclides in contaminated environmental samples; soil, vegetation and air filters. For this purpose the Neutron Activation Analysis (NAA) Laboratory at the Pakistan Institute of Nuclear Science and Technology (PINSTECH), an IAEA Regional Resource Unit (IAEA-RRU), along with 76 other well-known and relevant international laboratories were invited to participate in a regular proficiency programme. The measurement procedures employed, the problems encountered and the improvements and experience gained by the NAA Laboratory throughout this exercise are presented.

TL and EPR studies of Cu, Ag and P doped Li2B4O7 phosphor

Key characteristics of a newly prepared tissue-equivalent, highly sensitive thermoluminescence dosimeter, Li2B4O7:Cu,Ag,P, are presented. The material was developed at the Institute of Nuclear Sciences, Belgrade, in the form of sintered pellets. A new preparation procedure has greatly increased the sensitivity of the basic copper activated lithium borate and the glow curve of Li2B4O7 : Cu,Ag,P consists of a well-defined main dosimetric peak situated at about 460–465 K with a sensitivity which is about four to five times higher than that of LiF : Mg,Ti (TLD-100). The exceptionally good response features of Li2B4O7 : Cu,Ag,P are attributed to the incorporation of Cu as a dopant. Both low and high temperature emission spectra are presented and the origins of the various emission bands are considered. Additional data are provided from electron paramagnetic resonance measurements.

Optically and thermally stimulated luminescence characteristics of MgO:Tb3+

In this paper main optically stimulated luminescence (OSL) and thermoluminescence (TL) characteristics are presented of a newly synthesised material MgO doped with terbium (Tb) developed at the Institute of Nuclear Science, Vinca. A thermally stimulated emission spectrum showed the characteristic lines of Tb3+ in a wide range of wavelengths. The TL sensitivity of the main TL glow peak at 315 degrees C is 1.7 times higher than the TL of Al2O3:C. The highest OSL sensitivity was obtained under green lamp (500-570 nm) stimulation. The fast component in the OSL decay curve is 2.4 times faster than Al2O3:C. The OSL signal is linear with dose up to 10 Gy. The lower limit of detection was found to be 100 microGy. These first results show that the newly synthesised material has some promising properties for the application in radiation dosimetry.

National intercomparison exercise, ZH-A for the measurement of hafnium and zirconium in zirconium ores

A national intercomparison exercise was conducted to remove inconsistencies and improve analytical procedures in the measurement of hafnium and zirconium in zirconium ores. The ZH-A series of reference samples, prepared at the Pakistan Institute of Nuclear Science and Technology (PINSTECH), were used for this purpose. It was observed that measurement errors decreased with increasing Hf concentration (~298-17500 ppm) for most techniques, especially for AAS due to the sample preparation procedure required for this technique. Of all the tested techniques most reliable results were obtained with neutron activation analysis (NAA) for the measurement of Hf and Zr in such matrices.

Concept of an accelerator-driven subcritical research reactor within the TESLA accelerator installation

Study of a small accelerator-driven subcritical research reactor in the Vinča Institute of Nuclear Sciences was initiated in 1999. The idea was to extract a beam of medium-energy protons or deuterons from the TESLA accelerator installation, and to transport and inject it into the reactor. The reactor core was to be composed of the highly enriched uranium fuel elements. The reactor was designated as ADSRR-H. Since the use of this type of fuel elements was not recommended any more, the study of a small accelerator-driven subcritical research reactor employing the low-enriched uranium fuel elements began in 2004. The reactor was designated as ADSRR-L. We compare here the results of the initial computer simulations of ADSRR-H and ADSRR-L. The results have confirmed that our concept could be the basis for designing and construction of a low neutron flux model of the proposed accelerator-driven subcritical power reactor to be moderated and cooled by lead. Our objective is to study the physics and technologies necessary to design and construct ADSRR-L. The reactor would be used for development of nuclear techniques and technologies, and for basic and applied research in neutron physics, metrology, radiation protection and radiobiology.