International Nuclear Information System (INIS)

Uranium and thorium ores are the source of natural radionuclides. Briefly described are the original and current methods of long-lived nuclide separation ("2"3"8U, "2"3"5U, "2"2"6Ra, "2"3"0Th, "2"3"1Pa, "2"2"7Ac, "2"3"2Th, "2"2"8Ra+"2"2"8Ac, "2"2"8Th), some short-lived nuclides ("2"3"4Th and "2"2"8Ac), radon, short-lived radon daughter products and long-lived radon daughter products ("2"1"0Pb, "2"1"0Bi, "2"1"0Po). Some nuclides, such as "2"1"0Po or "2"3"1Pa can more easily be producedin reactors. (Ha).

Energy Technology Data Exchange (ETDEWEB)

Absolute fission rate measurements using modified National Bureau of Standards fission chambers were performed in the Fast Flux Test Facility at two core locations for isotopic deposits of {sup 232}Th, {sup 233}U, {sup 235}U, {sup 238}U, {sup 237}Np, {sup 239}Pu, {sup 240}Pu, and {sup 241}Pu. Monitor chamber results at a third location were analyzed to support other experiments involving passive dosimeter fission rate determinations.

International Nuclear Information System (INIS)

Description of program or function: Format: ENDFB-6 format; Nuclides: Th-232, U-233, U-234, U-235, U-236, U-238, Np-237, Np-238, Pu-238, Pu-239, Pu-240, Pu-241, Pu-242, Am-241, Am-242, Am-243, Cm-243, Cm-244, Cm-245, and from the spontaneous fission of Cm-242, Cm-244, and Cf-252. Origin: New evaluation (Crouch 1, 2, 3, 4; UKFY1; JEF-1). A new evaluation of fission product yields from the thermal, fast, and 14 MeV neutron-induced fission of the following nuclides has been prepared in ENDFB-VI format: "2"3"2Th, "2"3"3U, "2"3"4U, "2"3"5U, "2"3"6U, "2"3"8U, "2"3"7Np, "2"3"8Np, "2"3"8Pu, "2"3"9Pu, "2"4"0Pu, "2"4"1Pu, "2"4"2Pu, "2"4"1Am, "2"4"2"mAm, "2"4"3Am, "2"4"3Cm, "2"4"4Cm, "2"4"5Cm; and from the spontaneous fission of "2"4"2Cm, "2"4"4Cm, and "2"5"2Cf

Science.gov (United States)

The NCRP Wound Model, which describes the retention of selected radionuclides at the site of a contaminated wound and their uptake into the transfer compartment, has been combined with the ICRP element-specific systemic models for those radionuclides to derive dose coefficients for intakes via contaminated wounds. These coefficients can be used to generate derived regulatory guidance (i.e., the activity in a wound that would result in an effective dose of 20 or 50 mSv, or in some cases, a organ-equivalent dose of 500 mSv) and clinical decision guidance (i.e., activity levels that would indicate the need for consideration of medical intervention to remove activity from the wound site, administration of decorporation therapy or both). Data are provided for 38 radionuclides commonly encountered in various activities such as nuclear weapons, fuel fabrication or recycling, waste disposal, medicine, research, and nuclear power. These include 3H, 14C, 32P, 35S, 59Fe, 57,58,60Co, 85,89,90Sr, ...

Energy Technology Data Exchange (ETDEWEB)

A new method for the determination of {sup 237}Np and Pu isotopes in large soil samples has been developed that provides enhanced uranium removal to facilitate assay by inductively coupled plasma mass spectrometry (ICP-MS). This method allows rapid preconcentration and separation of plutonium and neptunium in large soil samples for the measurement of {sup 237}Np and Pu isotopes by ICP-MS. {sup 238}U can interfere with {sup 239}Pu measurement by ICP-MS as {sup 238}UH{sup +} mass overlap and {sup 237}Np via {sup 238}U peak tailing. The method provides enhanced removal of uranium by separating Pu and Np initially on TEVA Resin, then transferring Pu to DGA resin for additional purification. The decontamination factor for removal of uranium from plutonium for this method is greater than 1 x 10{sup 6}. Alpha spectrometry can also be applied so that the shorter-lived ...

Energy Technology Data Exchange (ETDEWEB)

Evaluation of nuclear data has been performed for {sup 237}Np, {sup 241}Am, {sup 242g}Am and {sup 242m}Am. Neutron data were obtained at energies from 20 to 250 MeV and combined with JENDL-3.3 data at 20 MeV. Evaluation of the proton data has been done from 1 to 250 MeV. The coupled channel optical model was used to obtain angular distributions for elastic and inelastic scattering and transmission coefficients. Pre-equilibrium exciton model and Hauser-Feshbach statistical model were used to describe neutron and charged particles emission from excited nuclei. These evaluation is the first work for producing full sets of evaluated file up to 250 MeV for {sup 237}Np and Americium isotopes. (author)

International Nuclear Information System (INIS)

A new method that allows rapid preconcentration and separation of plutonium and neptunium in water samples was developed for the measurement of "2"3"7Np and Pu isotopes by inductively-coupled plasma mass spectrometry (ICP-MS) and alpha spectrometry. "2"3"8U can interfere with "2"3"9Pu measurement by ICP-MS as "2"3"8UH"+ mass overlap and "2"3"7Np via peak tailing. The method provide enhanced removal of uranium by separating Pu and Np initially on TEVA Resin, then moving Pu to DGA resin for additional removal of uranium. The decontamination factor for uranium from Pu is almost 100,000 and the decontamination factor for U from Np is greater than 10,000. This method uses stacked extraction chromatography cartridges and vacuum box technology to facilitate rapid separations. Preconcentration is performed using a streamlined calcium phosphate precipitation method. Purified solutions are split between ICP-MS and alpha spectrometry so that long and short-lived Pu isotopes can be measured ...

International Nuclear Information System (INIS)

In nuclear fuel with a burn-up of 33 kg/t U and 52 kg/t U 15 transuranium nuclides "2"3"7Np to "2"4"6Cm have been determined by alpha and gamma spectroscopy after radiochemical separation. (author).

International Nuclear Information System (INIS)

Mass distribution in 28.5 MeV alpha particle induced fission of "2"3"2Th has been determined using gamma spectrometric technique. The chain yields of 24 different fission products covering both symmetric and asymmetric mass divisions were determined. The mass distribution was found to be asymmetric with peak positions at mass numbers 96 and 136 respectively while the peak to valley ratio was 3.86. The results are compared with the available literature on 14 MeV neutron induced fission of "2"3"5U. (orig.).

International Nuclear Information System (INIS)

The nuclide "2"4"1Am decays by alpha emission to "2"3"7Np. Most of the decays (84.6%) populate the excited level of "2"3"7Np with energy of 59.54 keV. Digital coincidence counting was applied to standardize a solution of "2"4"1Am by alpha-gamma coincidence counting with efficiency extrapolation. Electronic discrimination was implemented with a pressurized proportional counter and the results were compared with two other independent techniques: Liquid scintillation counting using the logical sum of double coincidences in a TDCR array and defined solid angle counting taking into account activity inhomogeneity in the active deposit. The results show consistency between the three methods within a limit of a 0.3%. An ampoule of this solution will be sent to the International Reference System (SIR) during 2009. Uncertainties were analysed and compared in detail for the three applied methods.

International Nuclear Information System (INIS)

A radioactively contaminated marine sediment core stemming from Irish Sea has been characterized by radiometric and mass spectrometric techniques as for "2"3"7Np, "2"4"1Am, "2"3"9Pu, "2"4"0Pu, "2"4"1Pu, "1"3"7Cs and "1"5"4Eu. The data obtained with independent methods in the framework of a QA/QC program as compared with the source term discharges, as well as with those reported in literature, are in good agreement. (author)

Energy Technology Data Exchange (ETDEWEB)

Neutron capture cross sections of actinides are of great relevance for the Transmutation of Nuclear Waste in Accelerator Driven Systems (ADS) and Generation-IV reactors. The neutron capture cross sections of {sup 237}Np and {sup 240}Pu in the range of 1 eV to 2 keV were measured at the n-TOF facility with a Total Absorption Calorimeter. The data have been analyzed with the SAMMY code. The corresponding covariance matrices have been generated. The final cross sections are presented and compared to the previously existing ones.The n-TOF {sup 237}Np {sigma}(n,{gamma}) is in agreement with the evaluated data files below 300 eV and its is lower by 10 to 15% up to 2 keV. This discrepancy with the evaluated data files is also observed in the capture cross section derived from the transmission measurements of Gressier et al. In the case of the {sup 240}Pu {sigma}(n,{gamma}), the n-TOF {sigma}(n,{gamma}) agrees ...

Energy Technology Data Exchange (ETDEWEB)

To get a considerable reduction of the radiotoxicity due to americium, a thermal neutron fluence of 2.10{sup 22} cm{sup -2} or a fast neutron fluence of 2.10{sup 24} cm{sup -2} is required. Irradiation in a thermal neutron flux leads to lower masses of {sup 234}U and precursors and of {sup 237}Np and precursors, but to higher curium masses and much higher neutron emission rates than irradiation in a fast neutron flux. Therefore, irradiation in a fast neutron flux has preference when multiple recycling is adopted. When once-through burning is applied, irradiation in a thermal neutron flux can be applied. Then irradiation in a heavy water reactor (HWR) has preference above irradiation in a PWR or in a high temperature gas-cooled reactor (HTGR). (authors) 4 refs.

International Nuclear Information System (INIS)

An accurate neutronics calculation of a local thermal environment within a fast reactor presents a major challenge. A method was previously described that used Monte Carlo techniques within a macrocell to make accurate and reasonably efficient design calculations for such an environment. This method is now being further optimized for the calculation of "2"3"8Pu production in the Fast Flux Test Facility (FFTF). Here, it is not only important to determine the "2"3"8Pu production from neutron capture in "2"3"7Np, but also to calculate the production of the contamination isotope "2"3"6Pu from high-energy (n,2n) and (#gamma#,n) reactions. The power of the Monte Carlo method to automatically include geometry and energy self-shielding is retained by optimization using fission neutron source biasing in both space and energy.

International Nuclear Information System (INIS)

Three blocks of non-welded tuff, one nominally one cubic foot (trial block) in volume and the other two, nominally one cubic meter (1 m3) in volume, were excavated from the Busted Butte Test Facility on the Nevada Test Site in 1999 and transported to the Atomic Energy of Canada Limited Whiteshell Laboratories in Pinawa, Manitoba. The trial block and one of the 1-m3 blocks were used for radionuclide migration experiments under unsaturated conditions; the remaining 1-m3 block was used for similar migration experiments under saturated conditions. After a vertical flow of synthetic transport solution was set up under unsaturated conditions, a suite of conservative and chemically reactive radionuclide tracers was injected at volumetric flow rates of 20 mL/hr in the trial block, and 10 mL/hr in two locations on the upper surface of the 1-m3 block. These flow rates correspond to infiltration rates of about 120 cm/year and about 17 cm/year, respectively. The duration of the migration ...

Energy Technology Data Exchange (ETDEWEB)

Nowadays there is a growing interest in the study of natural radioactivity levels, mainly of radionuclides; {sup 238}U, {sup 226}Ra, {sup 232}Th, {sup 40}K, and {sup 210}Pb present in the environment. The environmental radioactivity control is very important to obtain information on exposure of humans and vegetables to potential sources on natural radioactive occurrences. Industrial processes involving mining and extraction and production of oil foster concentration of radionuclides, contributing to the occurrence of what is known as 'TENORM' - Technologically Enhanced Naturally Occurring Radioactive Material. This work aims to assess the environmental radiological impact on the estuarine area of the Industrial Park of SUAPE, due the installation of an oil refinery and the consequent introduction on the environment of natural radioactive materials from other regions in that area. The radioisotopes {sup 238}U, {sup 226}Ra, {sup ...

Science.gov (United States)

Isotope separation of Ar, C, /sup 3/He, Kr, Ne, O, and Xe isotopes is reported. TiFeH/sub x/, TiCoH/sub x/, TiCuH/sub x/, and VH/sub x/ were studied using NMR (proton relaxation times). VD/sub x/ and VT/sub x/ were synthesized. The problem of calculating the valence state of Pu is discussed. A series solution to the plutonium (N,H) characteristic equation is suggested. Shipments of /sup 231/Pa, /sup 230/Th, and /sup 229/Th are reported. Separation and processing of /sup 234/U are also reported. Theoretical methods were developed to calculate temperature distributions as functions of water flow rate in liquid thermal diffusion columns. Diffusion coefficients were measured from 300 to 1200/sup 0/K for Kr-Xe and Kr-Ar. New thermal diffusion factors are submitted for Ne-Ar.

International Nuclear Information System (INIS)

In the framework of nuclear waste transmutation studies, the Mini-INCA project has been initiated at CEA/DSM with objectives to determine optimal conditions for transmutation and incineration of minor actinides (MA) in high intensity neutron fluxes. Our experimental tools based on alpha- and gamma-spectroscopy of the samples and the development of micro fission chambers could gather either microscopic information on nuclear reactions (total or partial cross sections for neutron capture and/or fission reactions) or macroscopic information on transmutation and incineration potentials. Neutron capture cross sections of selected actinides ("2"4"1Am, "2"4"2Am, "2"4"2Pu, "2"3"7Np) have already been measured at ILL, showing some discrepancies when compared to evaluated data libraries but in overall good agreement with recent data. The studies and possibilities offer by the MEGAPIE project to assess neutronic performances of a 1 MW spallation target and the incineration of MA in a ...

Energy Technology Data Exchange (ETDEWEB)

An intertidal estuarine sediment core was collected from Esk Estuary in the Irish Sea which had been contaminated by low-level radioactive liquid effluent from the nuclear fuel reprocessing plants at Sellafield, UK. The {sup 242}Cm and {sup 243,244}Cm radioactivity concentrations were determined to establish the present contamination levels compared with other radionuclides {sup 137}Cs, {sup 237}Np, {sup 238}Pu, {sup 239,240}Pu, {sup 241}Pu and {sup 241}Am. The results showed that {sup 242}Cm and {sup 244}Cm existed in the detectable levels in the Irish Sea sediment and the concentration of {sup 242m}Am was evaluated from that of {sup 242}Cm. The {sup 242m}Am/{sup 239,240}Pu and {sup 244}Cm/{sup 239,240}Pu inventory ratios in the sediment core were about 0.04% and 0.3%, respectively. The total amount of {sup 242m}Am discharged into the Irish Sea from the start of the operation of BNFL Sellafield in 1952 to 1988 was estimated to be 0.2-0.3 TBq. ...

Energy Technology Data Exchange (ETDEWEB)

Some crops of important nutritive requirements have been collected from farmlands located in Bitsichi an old tin mining town in north central region of Nigeria. The food crops were analyzed in order to determine trace element concentrations level using Neutron Activation Analysis (NAA). The activity concentrations due to natural radionuclides in the food samples and soil samples collected within the root zone of the crops were also determined using gamma-ray spectrometry (GRS). The NAA results obtained showed higher concentration of Potassium among the essential elements in all the crops. Calcium concentration in both maize and Guinea corn was below detection limit and also Zn in Green beans, sweet potato and cassava. The trace elements; Sc, Hf, Sm, and Th, were below detection limit in all the crops except in Green beans. Rubidium (Rb) and lanthanum (La) were below detection limits only in Cabbage. The activity concentrations of the natural radionuclides in the food samples were found ...

Energy Technology Data Exchange (ETDEWEB)

The activity concentrations of potassium, uranium and thorium in minerals and soil samples from a mining site in Ibadan, Southwestern Nigeria were measured using gamma ray spectroscopy method. Effective dose per annum has been calculated from the activity concentrations of dominant gamma-emitting natural radionuclides, potassium, uranium and thorium. Samples collected include minerals (beryl, quartz and feldspar), soil samples from the mining pits, heaps and undisturbed land around the mining site. The activity concentrations of {sup 40}K, {sup 238}U and {sup 232}Th, respectively in Bq kg-1 in the mineral samples were as follows: 1985 +- 16, 4.8 +- 0.9 and 11.8 +- 5.8 for beryl sample, 115.1 +- 27.9, 5.0 +- 1.3 and 6.3 +- 5.0 for feldspar samples and 1421 +- 122, <4.8 and 20.1 +- 3.5 for quartz samples. For the soil samples, the mean activity concentrations of {sup 40}K, {sup 238}U and {sup ...

International Nuclear Information System (INIS)

Measurements are presented of indoor radon levels made in a prototype house constructed partly of bauxite waste (red mud) and partly of conventional materials. The mud used contains higher than the average amounts of "2"2"6Ra and "2"3"2Th found in local building materials. The rates of exhalation of radon from the material used in the construction of the house are measured and employed with measured air change rates to make estimates of the average contribution of the various materials to the measured radon levels indoors. There is fairly good agreement between the two. The increment of radon related dose equivalents above background are also estimated and these are combined with previously determined gamma dose equivalents and used as a basis for assessing the acceptability of the practice of using red mud as a building material. (author)

International Nuclear Information System (INIS)

Oil and gas production and processing operations sometimes cause naturally occurring radioactive materials (NORM) to accumulate at elevated concentrations in by-product waste streams. The sources of most of the radioactivity are isotopes of "2"3"8U and "2"3"2Th series, which are naturally present in the subsurface formations from which oil and gas are produced. NORM waste may cause problems in the operations of installations by plugging perforations, clogging tubular and valves then restricting flow. Therefore, plants or equipment have to be refurbished and decontaminated before reuse to avoid radioactive waste or surface contaminated object. There are two options for safe disposal of scale and sludge produced from NORM Descaling Facility : 1- Injection into an abandoned production well. 2- The construction of a near surface depository. These options are assumed to be environmental friendly disposal options. (author)

International Nuclear Information System (INIS)

The talk will focus on spin-dependent competition between oblate and prolate shape minima in the potential energy landscape of "1"8"0Hf (the most neutron-rich stable isotope), mediated via the alignment of valence nucleons. Results of a prompt spectroscopic study, using deep inelastic reactions with Gammasphere and CHICO, bombarding a thin "2"3"2Th target with a "1"8"0Hf beam #approx#25% above the Coulomb barrier, will be presented. Nucleon alignments in both prolate and oblate minima will be discussed, as well as the favoring of oblate collective rotation at high spins, observed through a mixing with gamma vibrations built on the prolate shape.

Energy Technology Data Exchange (ETDEWEB)

Soils and food crops from a former tin mining location in a high background radiation area on the Jos-Plateau, Nigeria were collected and analyzed by gamma spectrometry to measure their contents of {sup 40}K, {sup 238}U and {sup 232}Th. As well as collecting samples, in situ dose rates on farms were measured using a precalibrated survey meter. Activity concentrations determined in food crops were compared with the local food derivatives or diets to investigate the possible removal or addition of radionuclides during food preparation by cooking or other means. Potassium-40 was found to contribute the highest activity in all the food products. The activity concentration of {sup 40}K, {sup 238}U and {sup 232}Th in local prepared diets ranged between 60 and 494 Bq kg{sup -1}, between BDL and 48 Bq kg{sup -1} and between BDL and 17 Bq kg{sup -1}, respectively. The internal effective dose to individuals from ...

International Nuclear Information System (INIS)

An intertidal estuarine sediment core was collected from Esk Estuary in the Irish Sea which had been contaminated by low-level radioactive liquid effluent from the nuclear fuel reprocessing plants at Sellafield, UK. The "2"4"2Cm and "2"4"3","2"4"4Cm radioactivity concentrations were determined to establish the present contamination levels compared with other radionuclides "1"3"7Cs, "2"3"7Np, "2"3"8Pu, "2"3"9","2"4"0Pu, "2"4"1Pu and "2"4"1Am. The results showed that "2"4"2Cm and "2"4"4Cm existed in the detectable levels in the Irish Sea sediment and the concentration of "2"4"2"mAm was evaluated from that of "2"4"2Cm. The "2"4"2"mAm/"2"3"9","2"4"0Pu and "2"4"4Cm/"2"3"9","2"4"0Pu inventory ratios in the sediment core were about 0.04% and 0.3%, respectively. The total amount of "2"4"2"mAm discharged into the Irish Sea from the start of the operation of BNFL Sellafield in 1952 to 1988 was estimated to be 0.2-0.3 TBq. (orig.)

International Nuclear Information System (INIS)

Neutron elastic and inelastic scattering cross sections of _2_3_8U and _2_3_2Th have been measured at the University of Lowell for states below 1.8 MeV. A time-of-flight (TOF) spectrometer was used. The disc-shaped scatterer was oriented to optimize energy resolutions for 200-to-500-keV neutrons. Neutrons were obtained via the _7Li(p,n)_7Be reaction. Targets were prepared by in-situ evaporation of Li onto a Ta backing. During the evaporation, the target thickness was monitored using a 5-m-flight-path TOF spectrometer; a typical target had a neutron thickness from 8 to 10 keV for Esub(p) = 2.25.MeV. Spectra were analyzed using the unfolding code TINA; standard peak shapes were obtained from codes LAGUE and LAPA. Results obtained will be presented.

International Nuclear Information System (INIS)

Several researchers have examined and achieved favourable results in connection with the building industry's use of red mud extracted in large quantities from the processing of bauxite. These days more and more precedence is being given to limiting the radiological dose to the population. In this study carried out in Hungary, the use of red mud, bauxite, and clay additives recommended for the production of special cements, were examined from a radiological aspect. "2"2"6Ra and "2"3"2Th activity concentrations measured in Hungarian bauxite, red mud and clay samples were significantly similar with the levels for such raw materials mentioned in international literature. Taking radiation protection aspects into consideration, none of these products can be directly used for building construction. Taking Hungarian and international values into consideration, a small amount of red mud, not exceeding 15% could be used for brick production, for example as a colouring material. However, beyond ...

Energy Technology Data Exchange (ETDEWEB)

Natural radioactive materials under certain conditions can reach hazardous radiological levels. The natural radionuclide ({sup 238}U, {sup 232}Th, {sup 40}K) contents of rock samples at various locations in the North Tushki area were investigated using gamma-spectrometric analysis. Estimates of the measured radionuclide content have been made for the absorbed dose rate of gamma radiation. The equivalent radium (R{sub eq}) and the external hazard index (H{sub ex}) which resulted from the natural radionuclides in soil are also calculated and tabulated. The studied samples have been collected from various rock exposures in the North Tushki area. The distribution of major oxides, U and Th were studied. It is found that the enrichment and depletion of the major oxides are mainly due to the effect of hydrothermal alteration, which caused mobility of some major oxides, which increases some elements and decreases others. It is important to mention that ...

International Nuclear Information System (INIS)

The cross sections for /sup 250/Fm, /sup 244-246/Cf, /sup 242-244/Cm, and /sup 242/Am/sup g/ produced by the /sup 12/C+ /sup 242/Pu and the /sup 16/O+ /sup 238/U reactions leading to the same compound nucleus of /sup 254/Fm have been measured by using radiochemical methods. The excitation functions show that the difference between the /sup 12/C+ /sup 242/Pu and the /sup 16/O+ /sup 238/U reactions can be attributed mainly to the Coulomb barriers. Our results were compared with others reported previously for /sup 22/Ne+ /sup 232/Th, /sup 12/C+ /sup 238/U, /sup 12/C+ /sup 240,241/Pu, /sup 13/C+ /sup 241/Pu, /sup 16/O+ /sup 233/U, and /sup 16/O+ /sup 242/Pu reaction systems, and support a mechanism involving transfer of #alpha#-particle clusters (C,Be,He) from projectile to target for the production of Cf and Cm isotopes.

Energy Technology Data Exchange (ETDEWEB)

The paper present the results of the study on D.U. (depleted uranium) contamination in the environment and possible effects on animal healths in the region o f Bujanovac. Samples of soil, feed, leaves, grass, lichen, moss, honey and water were collected randomly in 2003/2004 in the vicinity of the target area (500-1000 m) and 5 km from the target area. Activity of the radionuclides ({sup 226}Ra, {sup 232}Th, {sup 40}K, {sup 210}Pb, {sup 238}U, {sup 235}U, {sup 137}Cs, {sup 7}Be) in soils, grass, lichen, moss and honey was determined on Hp Ge detector (Canberra, relative efficiency 23%) by standard gamma spectrometry. Total alpha and beta activity in water was determined on proportional alpha/beta counter (Canberra 2400, efficiency for alpha emitters 11%, efficiency for beta emitters 30%). Non significantly higher values of concentrations of {sup 226}Ra, {sup 232}Th, {sup 238}U and {sup 235}U were ...

Energy Technology Data Exchange (ETDEWEB)

RangerMaster{trademark} is the embedded firmware for Quantrad Sensor`s integrated nuclear instrument package, the Ranger{trademark}. The Ranger{trademark}, which is both a gamma-ray and neutron detection system, was originally developed at Los Alamos National Laboratory for in situ surveys at the Plutonium Facility to confirm the presence of nuclear materials. The new RangerMaster{trademark} software expands the library of isotopes and simplifies the operation of the instrument by providing an easy mode suitable for untrained operators. The expanded library of the Ranger{trademark} now includes medical isotopes {sup 99}Tc, {sup 201}Tl, {sup 111}In, {sup 67}Ga, {sup 133}Xe, {sup 103}Pa, and {sup 131}I; industrial isotopes {sup 241}Am, {sup 57}Co, {sup 133}Ba, {sup 137}Cs, {sup 40}K, {sup 60}Co, {sup 232}Th, {sup 226}Ra, and {sup 207}Bi; and nuclear materials {sup 235}U, {sup 238}U, {sup 233}U, and {sup 239}Pu. To accomplish isotopic ...

International Nuclear Information System (INIS)

Taking into consideration India's limited reserves of natural and vast reserves of thorium, the fast reactor route holds a great promise for India's energy supply in future. The fast reactor fueled with "2"3"9Pu/"2"3"8U (unused or depleted) produces (breeds) more fissionable fuel material "2"3"9Pu than it consumes. Calculations show that a fast breeder reactor (FBR) increases energy potential of natural uranium by about 60 times. As the fast reactor can also convert "2"3"2Th into "2"3"3U which is a fissionable material, it can make India's thorium reserves a source of almost inexhaustible energy supply for a long time to come. Significant advantage of FBR plants cooled by sodium and their world-wide operating experience are reviewed. There are two main safety issues of FBR, one nuclear and the other non-nuclear. The nuclear issue concerns core disruptive accident and the non-nuclear one concerns the high chemical energy potential of sodium. These two issues are analysed and it is ...

International Nuclear Information System (INIS)

Natural radioactive materials under certain conditions can reach hazardous radiological levels. The natural radionuclide ("2"3"8U, "2"3"2Th, "4"0K) contents of rock samples at various locations in the North Tushki area were investigated using gamma-spectrometric analysis. Estimates of the measured radionuclide content have been made for the absorbed dose rate of gamma radiation. The equivalent radium (R_e_q) and the external hazard index (H_e_x) which resulted from the natural radionuclides in soil are also calculated and tabulated. The studied samples have been collected from various rock exposures in the North Tushki area. The distribution of major oxides, U and Th were studied. It is found that the enrichment and depletion of the major oxides are mainly due to the effect of hydrothermal alteration, which caused mobility of some major oxides, which increases some elements and decreases others. It is important to mention that the study area is far from the development region of the ...