Development of radioactivity estimation system considering radioactive nuclide movement

International Nuclear Information System (INIS)

Fukumura, Nobuo; Miyamoto, Yoshiaki

2010-01-01

A radioactivity estimation system considering radioactive nuclide movement is developed to integrate the established codes and the code system for decommissioning of sodium cooled fast reactor (FBR). The former are the codes for estimation of radioactivity movement in sodium coolant of fast reactor which are named SAFFIRE, PSYCHE and TTT. The latter code system is to estimate neutron irradiation activity (COSMARD-RRADO). It is paid special attention to keep the consistency of input data used among these codes and also the simplification of their interface. A new function is added to the estimation system, to estimate minor FP inventory caused by the fission of impurities contained in the coolant and slight fuel material attached on the fuel cladding. To check the evaluation system, the system is applied with radioactivity data of the preceding FBR such as BN-350, JOYO and Monju. Agreement between the analysis results and the measurement is well satisfactory. The uncertainty of the code system is within several tens per cent for the activation of primary coolant (Na-22) and factor of 2-4 for the estimation of radioactivity inventory in sodium coolant. (author)

Therapeutic result of radioactive nuclide 90Sr/90Y treatment in patients with benign prostatic hypertrophy (BPH)

International Nuclear Information System (INIS)

Chen Hanchao; Li Yuying

2008-01-01

Objective: To study the effect of radioactive nuclide 90 Sr/ 90 Y treatment in patients with benign prostatic hypertrophy (BPH). Methods: Sixty patients with BPH were treated with a course of transurethral radioactive nuclide 90 Sr/ 90 Y therapy. Results: The severity of BPH was assessed with four parameters: maximal flow rate (MFR), volume of residual urine (VRU), international prostatic symptom score (IPSS) and volume (size) of prostate. In this series, the total effective rate was 93.33% with no treatment- related mortality. Favorable changes of the parameters after a course of radioactive nuclide therapy were significant. Conclusion: Radioactive nuclide 90 Sr/ 90 Y therapy for patients with BPH was safe, easily performed and quite effective. This procedure is worth popularizing in appropriate patients. (authors)

Natural radio-nuclides in drinking water

International Nuclear Information System (INIS)

Deflorin, O.

2003-01-01

This article discusses the presence of radio-nuclides in Switzerland's drinking water. The article describes research done into the natural radioactivity to be found in various drinking water samples taken from the public water supply in the Canton of Grisons in eastern Switzerland. The various natural nuclides to be expected are listed and the methods used to take the samples are described. The results of the analysis are presented in the form of sketches showing the geographical distribution of the nuclide samples. Diagrams of the cumulative frequency of the quantities of nuclides found are presented, as are such diagrams for the yearly radioactive doses that the population is exposed to. The results and their consequences for the water supply are discussed in detail and further investigations to be made in the region are proposed

Investigation on natural radioactive nuclide contents of rock products in Xi'an construction materials market

International Nuclear Information System (INIS)

Zhou Chunlin; Han Feng; Shang Aiguo; Li Tiantuo; Guo Huiping; Yie Lichao; Li Guifang

2001-01-01

The author reports the investigation results on natural radioactive nuclide contents of rock products from Xi'an construction materials market. The products were classified according to the national standard. The results show that natural radioactive nuclide contents in sampled rock products are in normal radioactive background levels. The radio-activity ranges of 238 U, 226 Ra, 232 Th and 40 K are 2.7 - 181.8, 0.92 - 271.0, 0.63 - 148.0, 1.8 - 1245 Bq·kg -1 , respectively. According to the national standard (JC 518-93), the application of some rock products must be limited

NUCLIDES 2000: an electronic chart of the nuclides

International Nuclear Information System (INIS)

Galy, J.; Magill, J.

2000-01-01

Radionuclides have many applications in agriculture, medicine, industry and research. For basic information on such radioactive materials, the Chart of the Nuclides has proved to be an indispensable tool for obtaining data on radionuclides and working out qualitatively decay schemes and reaction paths. These Charts are, however, of limited use when one requires quantitative information on the decaying nuclide and its daughters. This was the motivation for the development of the NUCLIDES 2000 software package. The radioactive decay data used in NUCLIDES 2000 is based on the Joint Evaluated File (Jeff) version 2.2. The present version of the program contains decay data on approximately 2700 radionuclides. (authors)

Study on the environmental movements and distributions of natural radioactive nuclides on the granite area (II)

International Nuclear Information System (INIS)

Morishima, Hiroshige; Koga, Taeko

1999-03-01

The natural radionuclides as K-40, uranium decay series and thorium decay series etc. are widely distributed on environment, but are not uniformly. These have various forms as the sources of terrestrial environmental γ radiation and of radon and make wide fluctuation seasonal and spatially on the environment. We have selected Ikeda mineral spring district, Shimane pref., Misasa spa district, Tottori pref., Muro district, Hachibuse district, Nara pref. and Arima spa district, Hyogo-pref. for HBRA, and Kawanishi-shi, Hyogo pref. and Higashi-osaka-shi, Osaka pref. as CA. We have carried out the study on the environmental movement and distribution of natural radioactive nuclides containing radon and decay nuclides. Radon measurements have been carried using cup typed radon and thoron monitors, pico-rad method by active charcoal sampling and Pilon scintillation-cell by grub sampling. Accumulated radon monitors have been used with cellulose nitrate as solid state track detector. Rn-222 concentrations in air at Misasa spa ranged 2 - 150 Bq/m 3 outdoor and 8 - 194 Bq/m 3 indoor. Rn-222 concentrations on Misasa district, Asahi district and Takeda district geologically formed from granite strata are high, and those on Osika district and Mitoku district formed from volcanic rocks (Andesite and Basalt) are low level. Rn-222 concentration variations in well water used as drinking water were 2 - 138 Bq/l (mean value 31 Bq/l) and those in ground waters varied from non detectable to 4620 Bq/l (mean 875 Bq/l) on sampling time and places. Mean Rn-222 concentration in the spring water at Arima spa area, Hyogo prefecture is 26 Bq/l at Tansan spring source and the other spring sources are comparatively low level. (J.P.N.)

Distribution of radioactive constituents in river waters

International Nuclear Information System (INIS)

Herranz, M.; Elejalde, C.; Legarda, F.; Romero, F.

1994-01-01

For a research project on the distribution and evaluation of natural and artificial radioactive constituents in ecological segments of Biscay (northeast spain), the amounts of nuclides present in the main river waters were measured. Radioactive procedures include i) total alpha and beta indexes with a gas flow detector, dry residues near to 2 and 10 mg/ cm sup 2, respectively and counting periods of 1000 mn, ii) gamma emitters with a low level gamma spectrometer (Ge-HP detector + 8000 channels analyser) using the dry residue from 8 litres and a counting period of 4 days and iii) statistical treatment of data at 95% confidence.In this paper, ten water samples from the nervion river basin are included. Physical and chemical parameters of samples were also determined by standard procedures, because there is a sharp change in the composition of this river in the first part of the course. Radioactive constituents were identified as follows: a sample has a detectable alpha index, all samples contains beta emitters with a high variability, natural nuclides from uranium and thorium families were detected in some cases. A parallel behaviour is found between samples where K-40 and Cs-137 were found. The paper tries at last to find relations among chemical and radioactive constituents by the application of multivariate statistical methods, specially for the case of Cs-137, the only artificial nuclide identified in this work. 1 tab., 2 figs., 5 refs. (author)

Research on the reliability of measurement of natural radioactive nuclide concentration of U-238

Energy Technology Data Exchange (ETDEWEB)

Cha, Seok Ki; Kim, Gee Hyun [Dept. of Nuclear engineering, Univ. of SeJong, Seoul (Korea, Republic of); Joo, Sun Dong; Lee, Hoon [KoFONS, Seongnam (Korea, Republic of)

2016-12-15

Naturally occurred radioactive materials (NORM) can be found all around us and people are exposed to this no matter what they do or where they live. In this study, two indirect measurement methods of NORM U-238 has been reviewed; one that has used HPGe on the basis of the maintenance, and the other is disequilibrium theory of radioactive equilibrium relationships of mother and daughter nuclide at Decay-chain of NORM U-238. For this review, complicated pre-processing process (Breaking->Fusion->Chromatography->Electron deposit) has been used , and then carried out a comparative research with direct measurement method that makes use of and measures Alpha spectrometer. Through the experiment as above, we could infer the daughter nuclide whose radioactive equilibrium has been maintained with U-238. Therefore, we could find out that the daughter nuclide suitable to be applied to Gamma indirect measurement method was Th-234. Due to Pearson Correlation statistics, we could find out the reliability of the result value that has been analyzed by using Th-234.

Distribution of transuranic nuclides in soils: a review

International Nuclear Information System (INIS)

Essington, E.H.; Fowler, E.B.

1976-01-01

The literature is reviewed to ascertain the degree of movement and the distribution patterns for transuranic and uranium nuclides in soils. Typical plutonium and uranium profiles are presented and an attempt is made to identify unique characteristics causing deviation from an ideal distribution pattern. By far most of the distribution observations are with plutonium and little is reported for uranium and other transuranic nuclides

Long-term behaviour of radioactive nuclides in the environment

International Nuclear Information System (INIS)

Brechignac, F.; Moberg, L.; Suomela, M.

1999-01-01

Report of recent advances in Europe, regarding the long-term development of radioactive nuclides in the environment. The corresponding scientific findings from three projects - Peace, Landscape and Epora (involving 18 European laboratories) - have been collected together. These projects were managed by the IPSN for the European Commission (DG XII) in the framework of the programme 'Surete de la fission nucleaire' (Nuclear fission safety programme). (author)

Importance of individual fission nuclide to incontainment radioactive reading during PWR accidents

International Nuclear Information System (INIS)

Li Junfeng; Shi Zhongqi

2004-01-01

Containment radiation level is one of the most important base for core damage assessment and protective actions recommendation during accidents. Incontainment radioactive reading calculations is the precondition of using this kind of method. Importance of individual nuclides were compared during normal coolant release, gap release and core melt. Conclusions are deduced that when the spray is off, the radioactive reading in containment is mainly from iodine and noble gas, and the spray is on, the radioactive reading is mainly from noble gas. (authors)

Modeling for Colloid and Chelator Facilitated Nuclide Transport in Radioactive Waste Disposal System

International Nuclear Information System (INIS)

Lee, Youn Myoung; Jeong, Jong Tae

2010-08-01

A modeling study and development of a total system performance assessment (TSPA) program template, by which assessment of safety and performance for a radioactive waste repository with normal and/or abnormal nuclide release cases can be made has been developed. Colloid and chelator facilitated transport that is believed to result for faster nuclide transport in various mediabothinthegeosphereandbiospherehas been evaluated deterministically and probabilistically to demonstrate the capability of the template developed through this study. To this end colloid and chelator facilitated nuclide transport has been modeled rather strainghtforwardly with assumed data through this study by utilizing some powerful function offered by GoldSim. An evaluation in view of apparent influence of colloid and chelator on the nuclide transport in the various media in and around a repository system with data assumed are illustrated

Development of detection method for individual environmental particles containing alpha radioactive nuclides

International Nuclear Information System (INIS)

Esaka, Konomi; Yasuda, Kenichiro; Esaka, Fumitaka; Magara, Masaaki; Sakurai, Satoshi; Usuda, Shigekazu; Nakayama, Shinichi

2006-01-01

Artificial radioactive nuclides have been emitted from various sources and have fallen on the surface of the earth as fine particles. Although the characterization of the individual fallout particles is very important, their analysis is difficult. The purpose of this study is to develop a new detection method for individual objective particles containing radioactive nuclides in the environment. The soil or sediment sample was confined in a plastic film and the locations of objective particles were identified with alpha tracks created in a solid-state detectors (BARYOTRAK, Fukuvi Chemical, Ltd) stuck to the both sides of the plastic film. A piece of the film containing the objective particle was cut with a nitrogen laser for following individual particle analysis. This procedure allowed us to detect the objective particle from innumerable number of particles in the environment and characterize the individual particles. (author)

WIS decontamination factor demonstration test with radioactive nuclides

International Nuclear Information System (INIS)

Kanbe, Hiromi; Mayuzumi, Masami; Ono, Tetsuo; Nagae, Madoka; Sekiguchi, Ryosaku; Takaoku, Yoshinobu.

1987-01-01

A radioactive Waste Incineration System (WIS) with suspension combustion is noticed as effective volume reduction technology of low level radiactive wastes that are increasing every year. In order to demonstrate the decontamination efficiency of ceramic filter used on WIS, this test has been carried out with the test facilities as joint research of Central Research Institute of Electric Power Industry (CRIEPI) and Sumitomo Heavy Industries, Ltd. Miscellaneous combustible waste and power resin, to which 5 nuclides (Mn-54, Fe-59, Co-60, Zn-65, Cs-137) were added, were used as samples for incineration. As the result of the test, it was verified that Decontamination Factor (DF) of the single stage ceramic filter was usually kept over 10 5 for every nuclide, and from the results of above DF, over 10 8 is expected for real commercial plant as a total system. Therefore, it is realized that the off-gas clean up system of the WIS composed of only single stage of ceramic filter is capable of sufficiently efficient decontamination of exhaust gas to be released to stack. (author)

A computer code for calculation of radioactive nuclide generation and depletion, decay heat and γ ray spectrum. FPGS90

International Nuclear Information System (INIS)

Ihara, Hitoshi; Katakura, Jun-ichi; Nakagawa, Tsuneo

1995-11-01

In a nuclear reactor radioactive nuclides are generated and depleted with burning up of nuclear fuel. The radioactive nuclides, emitting γ ray and β ray, play role of radioactive source of decay heat in a reactor and radiation exposure. In safety evaluation of nuclear reactor and nuclear fuel cycle, it is needed to estimate the number of nuclides generated in nuclear fuel under various burn-up condition of many kinds of nuclear fuel used in a nuclear reactor. FPGS90 is a code calculating the number of nuclides, decay heat and spectrum of emitted γ ray from fission products produced in a nuclear fuel under the various kinds of burn-up condition. The nuclear data library used in FPGS90 code is the library 'JNDC Nuclear Data Library of Fission Products - second version -', which is compiled by working group of Japanese Nuclear Data Committee for evaluating decay heat in a reactor. The code has a function of processing a so-called evaluated nuclear data file such as ENDF/B, JENDL, ENSDF and so on. It also has a function of making figures of calculated results. Using FPGS90 code it is possible to do all works from making library, calculating nuclide generation and decay heat through making figures of the calculated results. (author)

A computer code for calculation of radioactive nuclide generation and depletion, decay heat and {gamma} ray spectrum. FPGS90

Energy Technology Data Exchange (ETDEWEB)

Ihara, Hitoshi; Katakura, Jun-ichi; Nakagawa, Tsuneo [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

1995-11-01

In a nuclear reactor radioactive nuclides are generated and depleted with burning up of nuclear fuel. The radioactive nuclides, emitting {gamma} ray and {beta} ray, play role of radioactive source of decay heat in a reactor and radiation exposure. In safety evaluation of nuclear reactor and nuclear fuel cycle, it is needed to estimate the number of nuclides generated in nuclear fuel under various burn-up condition of many kinds of nuclear fuel used in a nuclear reactor. FPGS90 is a code calculating the number of nuclides, decay heat and spectrum of emitted {gamma} ray from fission products produced in a nuclear fuel under the various kinds of burn-up condition. The nuclear data library used in FPGS90 code is the library `JNDC Nuclear Data Library of Fission Products - second version -`, which is compiled by working group of Japanese Nuclear Data Committee for evaluating decay heat in a reactor. The code has a function of processing a so-called evaluated nuclear data file such as ENDF/B, JENDL, ENSDF and so on. It also has a function of making figures of calculated results. Using FPGS90 code it is possible to do all works from making library, calculating nuclide generation and decay heat through making figures of the calculated results. (author).

Novel reprocessing methods with nuclide separation for volume reduction of high level radioactive waste

International Nuclear Information System (INIS)

Suzuki, Tatsuya

2015-01-01

We have proposed the reprocessing system with nuclide separation processes based on the chromatographic technique in the hydrochloric acid solution system. Our proposing system consists of the dissolution process, the reprocessing process, the MA separation process, and nuclide separation processes. In our proposing processes, the pyridine resin is used as a main separation media. We expect that our proposing will contribute to that volume reduction of high level radioactive waste by combining the transmutation techniques, usage of valuable elements, and so on. (author)

A study on nuclide migration in buffer materials and rocks for geological disposal of radioactive waste

International Nuclear Information System (INIS)

Sato, Haruo

1998-01-01

This thesis summarizes the results investigated in order to establish a basic theory on the predictive method of diffusion coefficients of nuclides in compacted sodium bentonite which is a candidate buffer material and in representative rocks for the geological disposal of radioactive waste by measuring the pore structural factors of the compacted bentonite and rocks such as porosity and tortuosity, measuring diffusion coefficients of nuclides in the bentonite and rocks, acquiring basic data on diffusion and developing diffusion models which can quantitatively predict nuclide migration in long-term. (J.P.N.). 117 refs

Efficiency Of Transuranium Nuclides Transmutation

International Nuclear Information System (INIS)

Kazansky, Yu.A.; Klinov, D.A.; Semenov, E.V.

2002-01-01

One of the ways to create a wasteless nuclear power is based on transmutation of spent fuel nuclides. In particular, it is considered that the radioactivity of the nuclear power wastes should be the same (or smaller), than radioactivity of the uranium and the thorium extracted from entrails of the Earth. The problem of fission fragments transmutation efficiency was considered in article, where, in particular, the concepts of transmutation factor and the ''generalised'' index of biological hazard of the radioactive nuclides were entered. The transmutation efficiency has appeared to be a function of time and, naturally, dependent on nuclear power activity scenario, from neutron flux, absorption cross-sections of the nuclides under transmutation and on the rate of their formation in reactors. In the present paper the efficiency of the transmutation of transuranium nuclides is considered

Programme of research into the management and storage of radioactive waste, nuclide migration studies, and mathematical modelling

International Nuclear Information System (INIS)

1982-01-01

The progress of the work is reported under the headings: nuclide migration studies (nuclide-rock interactions; physico-chemical effects; field experiments; groundwater dating); mathematical modelling (calculation of steady groundwater flow using NAMMU; comparison of thermally and naturally driven flows near a radioactive waste repository; diffusion of radionuclides into a rock matrix; radionuclide migration). (U.K.)

Modified microspheres for cleaning liquid wastes from radioactive nuclides

International Nuclear Information System (INIS)

Danilin, Lev; Drozhzhin, Valery

2007-01-01

An effective solution of nuclear industry problems related to deactivation of technological and natural waters polluted with toxic and radioactive elements is the development of inorganic sorbents capable of not only withdrawing radioactive nuclides, but also of providing their subsequent conservation under conditions of long-term storage. A successful technical approach to creation of sorbents can be the use of hollow aluminosilicate microspheres. Such microspheres are formed from mineral additives during coal burning in furnaces of boiler units of electric power stations. Despite some reduction in exchange capacity per a mass unit of sorbents the latter have high kinetic characteristics that makes it possible to carry out the sorption process both in static and dynamic modes. Taking into account large industrial resources of microspheres as by-products of electric power stations, a comparative simplicity of the modification process, as well as good kinetic and capacitor characteristics, this class of sorbents can be considered promising enough for solving the problems of cleaning liquid radioactive wastes of various pollution levels. (authors)

Measurements of neutron cross sections of radioactive waste nuclides

Energy Technology Data Exchange (ETDEWEB)

Katoh, Toshio [Gifu College of Medical Technology, Seki, Gifu (Japan); Harada, Hideo; Nakamura, Shoji; Tanase, Masakazu; Hatsukawa, Yuichi

1998-01-01

Accurate nuclear reaction cross sections of radioactive fission products and transuranic elements are required for research on nuclear transmutation methods in nuclear waste management. Important fission products in the nuclear waste management are {sup 137}Cs, {sup 135}Cs, {sup 90}Sr, {sup 99}Tc and {sup 129}I because of their large fission yields and long half-lives. The present authors have measured the neutron capture cross sections and resonance integrals of {sup 137}Cs, {sup 90}Sr and {sup 99}Tc. The purpose of this study is to measure the neutron capture cross sections and resonance integrals of nuclides, {sup 129}I and {sup 135}Cs accurately. Preliminary experiments were performed by using Rikkyo University Reactor and JRR-3 reactor at Japan Atomic Energy Research Institute (JAERI). Then, it was decided to measure the cross section and resonance integral of {sup 135}Cs by using the JRR-3 Reactor because this measurement required a high flux reactor. On the other hand, those of {sup 129}I were measured at the Rikkyo Reactor because the product nuclides, {sup 130}I and {sup 130m}I, have short half-lives and this reactor is suitable for the study of short lived nuclide. In this report, the measurements of the cross section and resonance integral of {sup 135}Cs are described. To obtain reliable values of the cross section and resonance integral of {sup 135}Cs(n, {gamma}){sup 136}Cs reaction, a quadrupole mass spectrometer was used for the mass analysis of nuclide in the sample. A progress report on the cross section of {sup 134}Cs, a neighbour of {sup 135}Cs, is included in this report. A report on {sup 129}I will be presented in the Report on the Joint-Use of Rikkyo University Reactor. (author)

Detailed deposition density maps constructed by large-scale soil sampling for gamma-ray emitting radioactive nuclides from the Fukushima Dai-ichi Nuclear Power Plant accident.

Science.gov (United States)

Saito, Kimiaki; Tanihata, Isao; Fujiwara, Mamoru; Saito, Takashi; Shimoura, Susumu; Otsuka, Takaharu; Onda, Yuichi; Hoshi, Masaharu; Ikeuchi, Yoshihiro; Takahashi, Fumiaki; Kinouchi, Nobuyuki; Saegusa, Jun; Seki, Akiyuki; Takemiya, Hiroshi; Shibata, Tokushi

2015-01-01

Soil deposition density maps of gamma-ray emitting radioactive nuclides from the Fukushima Dai-ichi Nuclear Power Plant (NPP) accident were constructed on the basis of results from large-scale soil sampling. In total 10,915 soil samples were collected at 2168 locations. Gamma rays emitted from the samples were measured by Ge detectors and analyzed using a reliable unified method. The determined radioactivity was corrected to that of June 14, 2011 by considering the intrinsic decay constant of each nuclide. Finally the deposition maps were created for (134)Cs, (137)Cs, (131)I, (129m)Te and (110m)Ag. The radioactivity ratio of (134)Cs-(137)Cs was almost constant at 0.91 regardless of the locations of soil sampling. The radioactivity ratios of (131)I and (129m)Te-(137)Cs were relatively high in the regions south of the Fukushima NPP site. Effective doses for 50 y after the accident were evaluated for external and inhalation exposures due to the observed radioactive nuclides. The radiation doses from radioactive cesium were found to be much higher than those from the other radioactive nuclides. Copyright © 2014 The Authors. Published by Elsevier Ltd.. All rights reserved.

A prospect of the administration against problems of environmental contamination caused by radioactive nuclides

International Nuclear Information System (INIS)

Osako, Masahiro

2012-01-01

At first, focusing on the problem of radioactive contaminated wastes caused by Fukushima Daiichi Nuclear Accident, the Author described an outline of the waste management policy based on the law on special measures against the environmental contamination by radioactive nuclides. Next, the Author discussed a prospect of the environmental administration against the radioactive contamination problem. The most important mission of the environmental administration for the future must be to establish a social basis for the sustainable development, in other words the building-up of a newly social value added, through the measures against this unprecedented disaster. (author)

WWW chart of the nuclides

International Nuclear Information System (INIS)

Huang Xiaolong; Zhou Chunmei; Zhuang Youxiang; Zhao Zhixiang; Golashvili, T.V.; Chechev, V.P.

2000-01-01

WWW chart of the nuclides was established on the basis of the latest evaluations of nuclear structure and decay data. By viewing WWW chart of the nuclides, one can retrieve the fundamental data of nuclide such as atomic mass, abundance, spin and parity; the decay mode, branching ratio, half-life and Q-value of radioactive nuclide, energy and intensity of strong γ-ray, etc. The URL (Uniform Resource Locator) of WWW chart of the nuclides is: http://myhome.py.gd.cn/chart/index,asp

Radioactive nuclides in the marine environment

International Nuclear Information System (INIS)

Yamato, Aiji; Miyagawa, Naoto; Miyanaga, Naotake

1984-01-01

To investigate behaviour of 95 Zr, 95 Nb in the marine environment, various samples have been collected and measured by means of Ge(Li) γ-ray spectrometry and/or radiochemical analysis during a period from 1974 to 1982 at coastal area of Tokai-mura, Ibaraki prefecture. Concentration of the nuclides in seaweeds increased remarkably after atmospheric nuclear detonation by P.R. of China, and the activity ratio between the nuclides changed by time was not fit well by the transient decay equation. Concentration variation in sea water was smaller than that in sea weeds, and the minimum change in sea sediment. Increase of concentration in these environmental samples was observed in chronological order of sea water, sea weeds then sediment after detonations, suggesting that the uptake of the nuclides by these sea weeds from sea water is faster than that via root. Observed concentration factors on the nuclides by sea weeds were calculated from the observed concentrations in sea water and sea weeds. Maximum values on 95 Zr and 95 Nb were 2110, 2150, respectively for Ecklonia cava and Eisenia bicyclis. (author)

Radionuclide distributions in sediment cores retrieved from marine radioactive waste dumpsites

International Nuclear Information System (INIS)

Bowen, V.T.; Livingston, H.D.

1981-01-01

The concentrations, distributions and inventories of 55 Fe, 60 Co, 137 Cs, 134 Cs, 238 Pu, sup(239,240)Pu, 241 Am, 244 Cm and 242 Cm were measured in sediment samples collected in 1975-1976 from some Atlantic and Pacific sites used by the United States of America from 1946-1970 to dump solidified radioactive waste. Criteria used to distinguish waste-contaminated sediments from fallout-contaminated sediments include deviations of nuclide concentrations, inventories, internuclide ratios and depth distributions. The detection of nuclides absent from fallout is a further indicator. The data set used in comparing dumpsite sediment radioactivity with non-dumpsite radioactivity comes from a population of 11 North Atlantic cores in the depth range 2000-4000 m. A further set of 19 cores from the central North Pacific provides an interesting contrast to the data set for the shallower sediments closer to the coasts. The principal conclusion drawn from consideration of a large body of data, especially for 15 sediment cores from the Atlantic dumpsite, is that contamination is extremely localized with respect to the sources from which the waste is believed to originate. The majority of cores from both dumpsites are indistinguishable from populations of cores contaminated only by world-wide fallout. Clearly, contaminated sediments from both dumpsites show evidence of the introduction of waste radioactivity below the sediment surface before subsequent redistribution by in-sediment processes. These findings have significance for the selection and monitoring of sites to be used in connection with the ocean disposal of radioactive waste. (author)

Nuclides 2000: an electronic chart of the nuclides on CD-ROM

International Nuclear Information System (INIS)

Magill, J.

2000-01-01

The 'Nuclides 2000' software package is an electronic chart of the nuclides, available on CD-ROM for Microsoft Windows operating systems, which offers extensive basic information on physics and radiology of the familiar nuclides. Moreover, 'Nuclides 2000' contains codes for a number of applications which allow the required data to be computed quickly and reliably by means of interactive user guidance. The data and codes are supplemented by information in the format of contributions on the history of radioactivity and radiochemistry, and on subjects of interest in physics, such as C-14 dating and the generation of Ti-44 in a supernova, and by a link collection of Internet addresses. As a detailed database, 'Nuclides 2000' can be used for teaching, research, and for practical applications. (orig.) [de

Radioactive fallout nuclides in a peat-bog ecosystem

International Nuclear Information System (INIS)

Pausch, G.; Hofmann, W.; Steger, F.; Tuerk, R.

1996-01-01

The Province of Salzburg belongs to the regions with the highest contamination from the Chernobyl-fallout outside the former USSR. The peat-bog investigated in this study is situated in Koppl, east of Salzburg. A peat-bog is a special example of an ecosystem, which is generally not disturbed by human activities because it is under strict nature-conservation and whose soil structure is not affected by animal activities from moles and earthworms. Peat-bogs are characterized by acidic soils which are high in organic material and low in clay mineral content. A number of previous studies have demonstrated that especially in peat-bogs and especially in the Koppl-peat-bog very high amounts of radioactive fallout nuclides from the Chernobyl accident and from the bomb-testings could be found

The Study on Radioactive Nuclide Distributions within a Fuel Rod by Tomographic Gamma Scanning Method

International Nuclear Information System (INIS)

Quanhu, Zhang; Lee, H. K.; Hong, K. P.; Choo, Y. S.; Kim, D. S.

2005-06-01

Based on the specified need of the IMEF, the feasibility of Tomographic Gamma Scanning (TGS) technique has been investigated for its potential for non-destructive gamma scanning measurements of irradiated fuel rods. TGS technique has been developed for determining some radioactive isotopes' distributions of a fuel rod in hot cell. The results obtained from the simulation model extracting from real gamma scanning experimental condition in this work by new developed computer simulation codes confirmed that the gamma emission TGS technique has potential for determination of radioactive isotopes' distributions of a fuel rod. In order to verify the simulation codes, we have designed several computation schemes for both 3 by 3 and 10 by 10 fuel rod model under present situation at M1 hot cell in IMEF. The results which relative errors are less than 10% show that we have simulated and implemented determination of radioactive isotopes' distributions on simulated fuel rod by TGS technique successfully

Radioactive nuclides in sewage sludges and problems associated with their utilisation or dumping

International Nuclear Information System (INIS)

Schneider, P.; Brunner, P.; Tiefenbrunner, F.; Dierich, M.P.

1990-01-01

In a sewage plant with radioactively contaminated sewage an accumulation of radionuclides was found in the sewage sludge. The specific activities are in inverse proportion to the water content of the sewage sludge, the dehydrated sewage sludge having the highest specific activities. The retained radionuclides seem to be firmly accumulated in the sludge. Nevertheless, they are in a form which can be utilised by plants. This was demonstrated in experiments with Trifolium Repens and Secale Cereale where the rate of absorption was 15-33% (in Ci/kg dry weight per plant: nCi/kg dry weight soil x 100). Thus there are problems associated with using radioactively contaminated sewage sludge as a fertiliser. In further experiments to extract radioactive nuclides from ashed sewage sludge it was shown that acidifying the aqueous phase results in an increase in the level of radioactivity in the eluated fractions. (author)

Study of particle size distribution and formation mechanism of radioactive aerosols generated in high-energy neutron fields

CERN Document Server

Endo, A; Noguchi, H; Tanaka, S; Iida, T; Furuichi, S; Kanda, Y; Oki, Y

2003-01-01

The size distributions of sup 3 sup 8 Cl, sup 3 sup 9 Cl, sup 8 sup 2 Br and sup 8 sup 4 Br aerosols generated by irradiations of argon and krypton gases containing di-octyl phthalate (DOP) aerosols with 45 MeV and 65 MeV quasi-monoenergetic neutrons were measured in order to study the formation mechanism of radioactive particles in high energy radiation fields. The effects of the size distribution of the radioactive aerosols on the size of the added DOP aerosols, the energy of the neutrons and the kinds of nuclides were studied. The observed size distributions of the radioactive particles were explained by attachment of the radioactive atoms generated by the neutron-induced reactions to the DOP aerosols. (author)

Interactive information system on the nuclear physics properties of nuclides and radioactive decay chains

International Nuclear Information System (INIS)

Plyaskin, V.I.; Kosilov, R.A.; Manturov, G.N.

2001-01-01

A brief review is given of a computerized information system on the nuclear physics properties of nuclides and radioactive decay chains. The main difference between the system presented here and those already in existence is that these evaluated databases of nuclear physics constants are linked to a set of programs, thus enabling analysis of a wide range of problems regarding various nuclear physics applications. (author)

Nuclides and isotopes. Twelfth edition

International Nuclear Information System (INIS)

Anon.

1977-01-01

This explanatory booklet was designed to be used with the Chart of the Nuclides. It contains a brief history of the atomic theory of matter: ancient speculations, periodic properties of elements (Mendeleev table), radioactivity, early models of atomic structure, the Bohr atom, quantum numbers, nature of isotopes, artificial radioactivity, and neutron fission. Information on the pre-Fermi (natural) nuclear reactor at Oklo and the search for superheavy elements is given. The booklet also discusses information presented on the Chart and its coding: stable nuclides, metastable states, data display and color, isotopic abundances, neutron cross sections, spins and parities, fission yields, half-life variability, radioisotope power and production data, radioactive decay chains, and elements without names. The Periodic Table of the Elements is appended. 3 figures, 3 tables

Calculation of radioactivity of β-nuclides by CIEMAT/NIST method

International Nuclear Information System (INIS)

Shu Fujun; Zhang Shengdong; Ding Youqian; Sun Hongqing; Tang Peijia

2010-01-01

CIEMAT/NIST method for calculating radioactivity of β-nuclides was introduced in this paper. The influences of KB value and quenching parameter on the radioactivity computation of 241 Pu, 106 Ru/ 106 Rh, 63 Ni, 151 Sm and 14 C were studied by CIEMAT/NIST method with 3 H tracing. It is shown that the effect of KB value can be ignored if it varies in a proper range; Except for 106 Ru/ 106 Rh, the discrepancy between prediction and actual activity is lower than 2% in low quenching extent. However, it increases with quenching extent, and the largest discrepancy soars to nearly 13%. In addition, the reason for bad agreement of 106 Ru/ 106 Rh between prediction and actual activity was discussed. Efficiency calibration curves of 79 Se, 93 Zr and 107 Pd were also computed by CIEMAT/NIST method, compared with approximate replacement method or fitting and interpolation method. It is shown that CIEMAT/NIST method is no more accurate and suitable than the other two techniques. (authors)

Study on the environmental movements and distributions of natural radioactive nuclides on the granite area (III)

International Nuclear Information System (INIS)

Morishima, Hiroshige; Koga, Taeko

2000-03-01

The natural radionuclides as K-40, uranium decay series and thorium decay series etc. are widely distributed on environment, but are not uniformly. These have influences various forms as the sources of terrecial environmental γ radiation and of radon in to the human life environment and make wide fluctuation seasonal and spatially on the environment. The environmental radiation is higher than that of the other on the west Japan where generally consist rich of granite strata. We deeply appreciate in regard to natural radiation and would carry the studies on the movement and distribution of natural radioactive nuclides on high background radiation area consisted rich granite strata. We have selected and observed on Ikeda mineral spring district Ota-shi Shimane pref., Misasa spa district, Tohaku-gun, Tottori pref. on Chugoku area, Muro district Uda-gun, Hachibuse district, Nafa-shi Nara pref., and Arima spa district, Hyogo-pref., Kawanishi-shi, Hyogo pref. on Kinki area and Masutomi spa, Koma-gun, Yamanashi pref., for HBRA, and Higashi-osaka-shi, Osaka pref., for CA. We have carried out the study on the environmental movement and distribution of natural radioactive nuclides containing radon and decay nuclides, and reported these results on following; (1) Radon measurements have been carried using cup typed radon and thoron monitors which are easy handling in spite of need of long sampling period, pico-rad method by active charcoal sampling and Pilon scintillation-cell with 300 ml volume by grub sampling. Accumulated radon monitors have been used cellulose nitrate (LR-115 type II, Kodak Co.) as solid state track detector. Among these characteristics of radon monitors, though minimum detectable limit of cup method for 3 months sampling is higher than those by the other method, it is able to measure mean Rn-222 concentration for 3 months. Rn-222 concentration by pico-rad method is able to get briefly mean concentration for 24 hours, is small detector and many sample are

Measurement of Natural Radioactive Nuclide Concentrations and the Dose Estimation of Workers Originated from Radon in Manganese Ore Mine

International Nuclear Information System (INIS)

Mansour, N.A.; Hassan, N.M.; Blasy, M.R.

2013-01-01

Manganese ore is widely used in many industries. Such as ore contain natural radioactive nuclides at various concentrations. If this ore contain high concentrations of natural radioactive nuclides, workers handling them might be exposed to significant levels of radiation. Therefore it is important to determine the radioactive nuclides in this ore. Also the regulation of radon concentration at workplaces has gained an accentuated importance in all countries. Nevertheless, at this time there is no globally accepted workplace protocol that sets out safe radon concentration values. In this study the radon concentration measured by using an Alpha Guard radon monitor, the equilibrium factor which was greater than the value given in literature, effective radiation dose, which are necessary for the exact estimation of the radiation dose originating from radon. The regulation of radon concentration at workplaces has gained an accentuated importance in all countries. Approach: The natural radionuclides ( 238 U, 232 Th and 40 K) contents of manganese ore samples collected from Umm Bogma, southwest Sinai and from the mountain access Hamid South Eastern Desert, Egypt have been determined by low background spectroscopy using hyper-pure germanium (HPGe) detector. Results: The mean activities due to the three radionuclides ( 238 U, 232 Th and 40 K) were found to be 1500±65, 490±65 and 364±45 Bqkg -1 , respectively. The absorbed dose rate due to the natural radioactivity in samples under investigation ranged from 1522±45 → 1796±43 nGyh -1 . The radium equivalent activity varied from 3807±114→ 4446±133 Bqkg -1 .The representative external hazard index values for the corresponding samples are also estimated. Conclusion: The results of this assessment obtained by the gamma-ray spectroscopic analysis, have indicated that the levels of natural radioactivity were lower than the international recommended limits.

Method for the transmutation of nuclides

International Nuclear Information System (INIS)

1984-01-01

The invention relates to a method for the systematic and optimal manufacture of nuclides with beneficial properties as well as for the transmutation of noxious nuclides into innocuous ones, e.g. radioactive wastes. For that purpose, use is made of the periodic system of atoms and of the so-called twin-subshell model of nuclear structure, in order to trace the possible transformations of the nuclide through irradiation with appropriate particles or radiation. (G.J.P.)

Method of storing radioactive wastes

International Nuclear Information System (INIS)

Adachi, Toshio; Hiratake, Susumu.

1980-01-01

Purpose: To reduce the radiation doses externally irradiated from treated radioactive waste and also reduce the separation of radioactive nuclide due to external environmental factors such as air, water or the like. Method: Radioactive waste adhered with radioactive nuclide to solid material is molten to mix and submerge the radioactive nuclide adhered to the surface of the solid material into molten material. Then, the radioactive nuclide thus mixed is solidified to store the waste in solidified state. (Aizawa, K.)

Preparation of tracing source layer in simulation test of nuclide migration

International Nuclear Information System (INIS)

Zhao Yingjie; Ni Shiwei; Li Weijuan; Yamamoto, T.; Tanaka, T.; Komiya, T.

1993-01-01

In cooperative research between CIRP and JAERI on safety assessment for shallow land disposal of low level radioactive waste, a laboratory simulation test of nuclide migration was carried out, in which the undisturbed loess soil column sampled from CIRP' s field test site was used as testing material, three nuclides, Sr-85, Cs-137 and Co-60 were used as tracers. Special experiment on tracing method was carried out, which included measuring pH value of quartz sand in HCl solution, determining the eligible water content of quartz sand as tracer carrier, measuring distribution uniformity of nuclides in the tracing quartz sand, determining elution rate of nuclides from the tracing quartz sand and detecting activity uniformity of tracing source layer. The experiment results showed that the tracing source layer, in which fine quartz sand was used as tracer carrier, satisfied expected requirement. (1 fig.)

Selection of nuclide decay chains for use in the assessment of the radiological impact of geological repositories for radioactive waste

International Nuclear Information System (INIS)

Thorne, M.C.

1982-12-01

The criteria for selecting nuclide decay chains for use in the assessment of the radiological impact of geological repositories for radioactive waste are given. The reduced chains recommended for use with SYVAC are described. (author)

Relation between distribution coefficient of radioactive strontium and solid-liquid distribution ratio of background stable strontium

International Nuclear Information System (INIS)

Igarashi, Toshifumi; Mahara, Yasunori; Okamura, Masaki; Ashikawa, Nobuo.

1992-01-01

Distribution coefficients (K d ) of nuclides, which are defined as the ratio of the adsorbed concentration to the solution concentration, are important in predicting nuclide migration in the subsurface environment. This study was undertaken to contrust an effective method of determining the most pertinent K d value for simulating in situ distribution phenomena between the solid and liquid phases, by using background stable isotopes. This paper describes the applicability of this method to Sr by carrying out a batch Sr adsorption experiment where stable Sr coexisted with the radioactive isotope, 85 Sr, and by comparing the concentration distribution ratio of the background stable Sr with the K d value obtained by the batch experiment. The results showed that the K d of 85 Sr (K d85 ) agreed well with the K d of the coexisting stable Sr (K ds ) and that the two values decreased with an increase in the concentration of the stable Sr, when sand was used as an adsorbent. In addition, the K d85 corresponded to the ratio of the exchangeable solid-phase concentration of background stable Sr to the concentration of the background stable Sr in groundwater when the concentration of the coexisting stable Sr approached the background level. On the other hand, when powdered rock samples were used, the K d85 did not agree with the K ds , and the concentration distribution ratio of the background stable Sr was greater than the K d85 . This discrepancy might be due to the disequilibrium resulting from grinding the rock matrices. This suggests that measurement of the background stable Sr distribution ratio between the solid and liquid phases can be an effective method of estimating the K d of radioactive Sr when the groundwater is in satisfactory contact with the adsorption medium. (author)

[Radioactive nuclides in the marine environment--distribution and behaviour of 95Zr, 95Nb originated from fallout].

Science.gov (United States)

Yamato, A; Miyagawa, N; Miyanaga, N

1984-07-01

To investigate behaviour of 95Zr, 95Nb in the marine environment, various samples have been collected and measured by means of Ge(Li) gamma-ray spectrometry and/or radiochemical analysis during a period from 1974 to 1982 at coastal area of Tokai-mura, Ibaraki prefecture. Concentration of the nuclides in seaweeds increased remarkably after atmospheric nuclear detonation by P.R. of China, and the activity ratio between the nuclides changed by time was not fit well by the transient decay equation. Concentration variation in sea water was smaller than that in sea weeds, and the minimum change in sea sediment. Increase of concentration in these environmental samples was observed in chronological order of sea water, sea weeds then sediment after detonations, suggesting that the uptake of the nuclides by these sea weeds from sea water is faster than that via root. Observed concentration factors on the nuclides by sea weeds were calculated from the observed concentrations in sea water and sea weeds. Maximum values on 95Zr and 95Nb were 2110, 2150, respectively for Ecklonia cava and Eisenia bicyclis.

Method of separating radioactive nuclides from ion exchange resins

International Nuclear Information System (INIS)

Suzuki, Kazunori; Saikoku, Masami; Taneta, Daisuke; Yagi, Takuro.

1987-01-01

Purpose: To enable to safely process radioactive nuclides from spent ion exchange resins by using existent processing facilities. Method: Ion exchange resins in aqueous medium are at first placed to the ultrasonic wave irradiation site and put into such a state where clads and resins are easily separatable from each other by weakening the bonding force between them. Since the clads are magnetic material such as Fe 3 O 4 or NiFe 2 O 4 , the clads can be collected in the direction of the magnetic force by exerting the magnetic field simultaneously. The collected clads are transported by means of the aqueous medium to a collecting tank by removing the effect of magnetic field, for example, by interrupting the current supply to the electromagnet. Finally, they were subjected to stabilization and fixation into inorganic hardening agent such as cement hardener. Thus, processions can be made safely by using existent facilities. (Takahashi, M.)

A New Approach for the Determination of Dose Rate and Radioactivity for Detected Gamma Nuclides Using an Environmental Radiation Monitor Based on an NaI(Tl) Detector.

Science.gov (United States)

Ji, Young-Yong; Kim, Chang-Jong; Lim, Kyo-Sun; Lee, Wanno; Chang, Hyon-Sock; Chung, Kun Ho

2017-10-01

To expand the application of dose rate spectroscopy to the environment, the method using an environmental radiation monitor (ERM) based on a 3' × 3' NaI(Tl) detector was used to perform real-time monitoring of the dose rate and radioactivity for detected gamma nuclides in the ground around an ERM. Full-energy absorption peaks in the energy spectrum for dose rate were first identified to calculate the individual dose rates of Bi, Ac, Tl, and K distributed in the ground through interference correction because of the finite energy resolution of the NaI(Tl) detector used in an ERM. The radioactivity of the four natural radionuclides was then calculated from the in situ calibration factor-that is, the dose rate per unit curie-of the used ERM for the geometry of the ground in infinite half-space, which was theoretically estimated by Monte Carlo simulation. By an intercomparison using a portable HPGe and samples taken from the ground around an ERM, this method to calculate the dose rate and radioactivity of four nuclides using an ERM was experimentally verified and finally applied to remotely monitor them in real-time in the area in which the ERM had been installed.

Nuclide identifier and grat data reader application for ORIGEN output file

International Nuclear Information System (INIS)

Arif Isnaeni

2011-01-01

ORIGEN is a one-group depletion and radioactive decay computer code developed at the Oak Ridge National Laboratory (ORNL). ORIGEN takes one-group neutronics calculation providing various nuclear material characteristics (the buildup, decay and processing of radioactive materials). ORIGEN output is a text-based file, ORIGEN output file contains only numbers in the form of group data nuclide, nuclide identifier and grat. This application was created to facilitate data collection nuclide identifier and grat, this application also has a function to acquire mass number data and calculate mass (gram) for each nuclide. Output from these applications can be used for computer code data input for neutronic calculations such as MCNP. (author)

Radioactive consumer products

International Nuclear Information System (INIS)

Sato, Otomaru

1981-01-01

Present situation of utilizing the radioactive consumer products and exposure dose were reviewed with published data. Practically, consumer products are divided into three categories, (1) radioactive nuclides intentionally incorporated into radioluminous dye, ionization chambers for smoke detector, eliminator of static electricity, and glow lamp (2) natural radioactive nuclides contained in false teeth, porcelain, glass, and gas mantle (3) natural radioactive nuclides accumulated as industrial waste at the consumption of coal, petroleum, and natural gas or in fertilizer and materials for construction. (Nakanishi, T.)

Local tissue distribution of fissile nuclides

International Nuclear Information System (INIS)

Smith, J.M.

1981-01-01

Conventional tissue-section autoradiography of alpha-emitting actinide elements may require prohibitively long exposure times. Neutron-induced or fission-track autoradiography can be used for fissile nuclides such as 233 U, 235 U, and 239 Pu to circumvent this difficulty. The detection limit for these nuclides is about 4 x 10 -13 (weight fraction). This paper describes a specific technique for determining their microdistribution with histologically stained tissue sections

Survey monitoring of environmental radioactivity in Busan area

Energy Technology Data Exchange (ETDEWEB)

Yang, Han Soeb; Jang, Young A. [Busan Regional Monitoring Station, Busan (Korea, Republic of)

2003-12-15

At Regional Radioactivity Monitoring Station in Pusan have been measured periodically in 2003 gross beta activities in the airborne dust, fallout, precipitation and tap water and gamma exposure rates. Gamma nuclides in airborne dust, fallout and precipitation have also been monitored at the station. As a part of environmental radiation/radioactivity distribution survey around Busan foodstuffs, dust, drinking water (total 24ea) samples were taken from sampling sites which were selected by KINS. We analysis gamma nuclide for all. No significant changes from the previous survey have been found in both beta activities and gamma exposure rates. As the results of analyzing an gamma nuclide concentration in environmental samples in Pusan are fee of radiological contaminants.

Survey monitoring of environmental radioactivity in Busan area

International Nuclear Information System (INIS)

Yang, Han Soeb; Jang, Young A.

2003-12-01

At Regional Radioactivity Monitoring Station in Pusan have been measured periodically in 2003 gross beta activities in the airborne dust, fallout, precipitation and tap water and gamma exposure rates. Gamma nuclides in airborne dust, fallout and precipitation have also been monitored at the station. As a part of environmental radiation/radioactivity distribution survey around Busan foodstuffs, dust, drinking water (total 24ea) samples were taken from sampling sites which were selected by KINS. We analysis gamma nuclide for all. No significant changes from the previous survey have been found in both beta activities and gamma exposure rates. As the results of analyzing an gamma nuclide concentration in environmental samples in Pusan are fee of radiological contaminants

Method for the reprocessing of liquid wastes containing boric acid, radioactive antimony and other radioactive nuclides and similar, especially of the evaporator concentrates of nuclear power plants

International Nuclear Information System (INIS)

Doerr, A.

1978-01-01

The liquid wastes are evaporated, H 2 SO 4 and methanol are added, and the formed boric acid methylester is distilled off. The residue with Sb-124, Cs, Co and Mn is then stored two years until the activity of Sb-124 has decayed. Afterwards the radioactive nuclides are precipitated. (DG) [de

Accumulation and metabolism of radioactive nuclides

International Nuclear Information System (INIS)

Koyanagi, Taku

1981-01-01

After the injection of RI into the mantle cavity of Iidako (Octopus ocellatus), changes of whole body radioactivity were examined. Both the inorganic and organic forms of cobalt were most heavily distributed in the branchial heart. Cyanocobalamin was distributed in an extremely small amount in the liver, but was more distributed in the arms, or gonad. Mn and Zn were almost equally distributed in most portions, but were scarcely accumulated in the branchial heart. Like Co, Fe was ubiquitous in the branchial heart. In relation to the gel filtration pattern of the branchial heart extract, Co-chloride mostly flowed out into the small molecular zone, and cyano-cobalamin into the heavy molecular zone. Mn, Zn and Fe flowed out into similar portions, and the outflux of protein in absorption spectrum was also similar. Only Co and Fe were concentrated in the branchial heart, suggesting not only that their forms of accumulation were similar, but also that Mn and Zn were present in similar forms. (Chiba, N.)

Fuel burn-up distribution and transuranic nuclide contents produced at the first cycle operation of AP1000

International Nuclear Information System (INIS)

Jati Susilo; Jupiter Sitorus Pane

2016-01-01

AP1000 reactor core was designed with nominal power of 1154 MWe (3415 MWth), operated within life time of 60 years and cycle length of 18 months. For the first cycle, the AP1000 core uses three kinds of UO 2 enrichment, they are 2.35 w/o, 3.40 w/o and 4.45 w/o. Absorber materials such as ZrB 2 , Pyrex and Boron solution are used to compensate the excess reactivity at the beginning of cycle. In the core, U-235 fuels are burned by fission reaction and produce energy, fission products and new neutron. Because of the U-238 neutron absorption reaction, the high level radioactive waste of heavy nuclide transuranic such as Pu, Am, Cm and Np are also generated. They have a very long half life. The purpose of this study is to evaluate the result of fuel burn-up distribution and heavy nuclide transuranic contents produced by AP1000 at the end of first cycle operation (EOFC). Calculation of ¼ part of the AP1000 core in the 2 dimensional model has been done using SRAC2006 code with the module of COREBN/HIST. The input data called the table of macroscopic cross section, is calculated using module of PIJ. The result shows that the maximum fuel assembly (FA) burn-up is 27.04 GWD/MTU, that is still lower than allowed maximum burn-up of 62 GWD/MTU. Fuel loading position at the center/middle of the core will produce bigger burn-up and transuranic nuclide than one at the edges the of the core. The use of IFBA fuel just give a small effect to lessen the fuel burn-up and transuranic nuclide production. (author)

Studies on radioactivity monitoring proceedure for marine organisms

International Nuclear Information System (INIS)

Koyanagi, Taku; Hirano, Shigeki

1978-01-01

Suitability of several species of mollusca and seaweeds as indicator organisms for radioactivity monitoring of marine environment was examined by radioisotope tracer experiments or stable elements analyses from the standpoints of the affinities for radionuclides, the sampling procedures, and the distribution of radioactive and stable elements in the body of these organisms. Extremely high concentration factor of 54 Mn was shown by kidney of scallop suggesting the suitability for the efficient monitoring of the nuclide though the contribution of kidney to the weight of scallop was very small. Higher concentration of 54 Mn in midgut gland rather than kidney was observed in the case of other species of shellfishes but distribution of the nuclide among organs or tissues of the organisms varied during the period of intake and excretion. Ununiform distribution of radioactive and stable elements among the species of seaweeds and in the body of seaweeds observed by the tracer experiments and stable element analyses suggested the necessity of careful selection of the samples for monitoring of these nuclides. From the results of tracer experiments carried out in order to elucidate the relation between existing state of radionuclides in seawater and uptake by marine organisms, it was supposed that the complexed forms with inorganic or organic ligands in seawater were predominant species of radioactive cerium in seawater. (author)

Radioactive equilibria and disequilibria of U-series nuclides in erupting magmas from Izu arc volcanoes

International Nuclear Information System (INIS)

Sato, Jun; Kurihara, Yuichi; Takahashi, Masaomi

2009-01-01

Radioactive disequilibria among U-series nuclides are observed in the magmas from volcanoes in the world. Basaltic products from Izu arc volcanoes, including Izu-Oshima and Fuji volcanoes, show 230 Th 238 U and 226 Ra> 230 Th disequilibria, indicating that the addition of U-and Ra-rich fluid from the subducting slab to the mantle wedge at the magma genesis. The disequilibria of 226 Ra> 230 Th in the erupting magmas suggest that the timescale from magma genesis to the eruption may be less than 8000 years. (author)

Combination of digital autoradiography and alpha track analysis to reveal the distribution of definite alpha- and beta-emitting nuclides in contaminated samples

Energy Technology Data Exchange (ETDEWEB)

Vlasova, I. [Lomonosov MSU (Russian Federation); Kuzmenkova, N. [Vernadsky GEOKHI RAS (Russian Federation); Shiryaev, A. [Frumkin IPCE RAS (Russian Federation); Pryakhin, E. [Urals Research Center for Radiation Medicine (Russian Federation); Kalmykov, S.; Ivanov, I. [PA Mayak (Russian Federation)

2014-07-01

Digital autoradiography using Imaging Plate is commonly employed for searching 'hot' particles in the contaminated soil, sediment and aerosol probes. However digital radiography images combined with Alpha Track radiography data could provide much more information about micro-distribution of different alpha- and beta- nuclides. The discrimination method to estimate the distribution of radionuclides that are the main contributors to the total radioactivity ({sup 90}Sr/{sup 90}Y, {sup 137}Cs, {sup 241}Am) has been developed on the case of artificial reservoir V-17 (PA 'Mayak'). The bottom sediments and hydrobionts probes collected from V-17 along with the standards of {sup 137}Cs, {sup 90}Sr/{sup 90}Y and {sup 241}Am have been exposed for a short time (15 min) using a stack of 3 Imaging Plates (Cyclone Plus Storage Phosphor System, Perkin Elmer). The attenuation of photostimulated luminescence (PSL) intensity from layer to layer of the Imaging Plates depends on the type and energy of radiation. Integrated approach using PSL attenuation in the samples and standards (digital radiography) along with Alpha Track radiography and gamma-spectroscopy of the preparation was used to estimate the contribution of the main nuclides in specific parts of contaminated samples. The observation of the {sup 90}Sr/{sup 90}Y and {sup 137}Cs activity maxima could help to find the phases which are responsible for preferential sorption of the nuclides. Document available in abstract form only. (authors)

Measurement of radioactivity in rain

International Nuclear Information System (INIS)

Eivindson, T.

1985-01-01

The report gives a description of an ion-exchange surveillance- sampler for routine measurements of radioactivity in rain, and how the measurements are performed. Using the nuclides 85 Sr, 131 I and 137 Cs as tracers, experiments have been performed to determine the distribution of radioactivity in the ion-exchange column and the effectiveness of the column as a function of elutriation rate and temperature

Time-dependent radioactivity distribution in MAFF

International Nuclear Information System (INIS)

Nebel, F.; Zech, E.; Faestermann, T.; Kruecken, R.; Maier-Komor, P.; Assmann, W.; Szerypo, J.; Gross, M.; Kester, O.; Thirolf, P.G.; Groetzschel, R.

2006-01-01

The Munich Accelerator for Fission Fragments is planned to be installed at the FRM II in Garching. It will operate a uranium-carbide-loaded graphite matrix as a target for neutron-induced fission. The radioactive reaction fragments leave the ion source as both, atoms and ions. For radiation safety it is imperative to have a basic understanding of the fragment distribution within the beam line. Atoms leaving the graphite matrix will spread like a gas and stick to surfaces depending on their species. A probabilistic Monte-Carlo approach is used to predict the surface coating of internal surfaces of the beam line for all fission nuclides. To decrease calculation time, the problem is reduced to two dimensions with the surface areas being a measure for the probability, that they are hit by a particle. The program is completely time dependent to implement radioactive decay. Ions leaving the fission ion source are transported by electrostatic means towards the mass pre-separator, a low-resolution dipole magnet with a complex slit system in the focal plane. All unwanted ions are stopped at the slits, resulting in a high level of radioactive contamination. While it is advantageous for shielding purposes to have the majority of the contamination in one point, precautions must be taken to ensure that it stays that way. Material corrosion caused by sputtering will release previously implanted radionuclides. To reduce this effect, different methods are under investigation, one of which is changing the slit geometry. The considered designs will be described and experimental results will be shown

Modelling the reactive-path between pyrite and radioactive nuclides

International Nuclear Information System (INIS)

Kang Mingliang; Wu Shijun; Dou Shunmei; Chen Fanrong; Yang Yongqiang

2008-01-01

The mobility of redox sensitive nuclides is largely dependent on their valence state. The radionuclides that make the dominant contributions to final dose calculations are redox sensitive. Almost all the radionuclides (except 129 I) have higher mobility at high valence state, and correspond to immobilization at low valence state due to the much lower solubility. Pyrite is an ubiquitous and stable mineral in geological environment, and would be used as a low-cost long time reductant for the immobilization of radionuclides. However, pyrite oxidation is supposed to generate acid, which will enhance the mobility of nuclides. In this paper, the reaction path of the reactions between radionuclides (U, Se and Tc) and pyrite in the groundwater from Wuyi well in Beishan area of China has been simulated using geochemical modeling software. According to the results, pyrite can reduce high valence nuclides to a dinky-level effectively, with the pH slightly increasing under anaerobic condition that is common in deep nuclear waste repositories. (authors)

Investigation on the movements and the distributions of radon, thoron and their decay nuclides on the life circumstances

International Nuclear Information System (INIS)

Morishima, Hiroshige; Koga, Taeko

2001-03-01

UNSCEAR (2000) reported that the effective doses due to the inhalation of radon and its decay nuclides account on average of the all world for about one-half of all natural sources of radiation. These have great influences on various forms as the sources of terrecial environmental γ radiation and of radon on our life circumstances. Radon and thoron, which are natural gaseous radioactive nuclides released out of rocks and soil etc. are chemical inert and electrically uncharged, but they in the air can spontaneously decay to other metal atoms. And they made a wide fluctuation seasonally and spatially on the environment, but these are not uniformly. We have selected and observed on Misasa spa district, Tottori pref., Kawanishi-shi, Hyogo pref. and Masutomi spa, Yamanashi pref., for HBRA, and Higashi-osaka-shi, Osaka pref., for CA. We have carried out the study on the environmental movement and distribution of natural radioactive nuclides containing radon, thoron and their decay nuclides, and reported these results on following; (1) Radon measurements have been carried using a small pico-rad detector and many sampling points and Pilon scintillation-cell with 300 ml volume by grub sampling. Mean radon concentrations of get briefly for 24 hours are measured to be available on draw of the concentration distribution map. (2) We continued time cource variation of mean radon concentrations on same private house of Misasa spa district. Mean radon concentrations in air for 6 years were fluctuated 6.7-50 Bq/m 3 and 23-170 Bq/m 3 indoor. The mean concentrations on summer and rain season is low level at open-door situation and that on winter is high, as same as these on Kawanishi Hyogo pref.. It was shown that radon outdoor concentrations variation in time course almost have a similar tendency with indoor and the life situation of air ventilation and conditioning are more influenced than variation on area condition. (3) Radon concentrations on Masutomi spa districts, Yamanashi

Radioactive fall-out from the Chernobyl disaster, and its aftermath in Central Europe

International Nuclear Information System (INIS)

Mueller-Broich, A.

1986-01-01

Radioactive fall-out originating from the disaster of the nuclear power station at Chernobyl in the Soviet Union was measured in Bavaria and other parts of Central Europe. Nuclide composition and spatial distribution of fall-out are presented and compared to radioactive debris from nuclear bomb tests. The uptake of radioactive material by plants and its passage into human food is discussed. The contribution of direct deposition, redistribution within plants and transfer from soil into plants is considered. Factors determining the paths of radioactive material into milk and meat are outlined. Safety precautions against excessive incorporation of radioactivity issued by the authorities are given. Irradiation of humans from external and internal fall-out is assessed. Nuclides composition is shown to be of major importance only for internal radiation. In view of the dominating abundance of radioiodine and radiocesium the differing physical and biochemical qualities of these nuclides are described in more detail. Finally, the resulting risk of cancer induction including leukemia is considered

Radionuclide distributions in sediments of marine areas used for dumping solidified radioactive wastes

International Nuclear Information System (INIS)

Bowen, V.T.; Livingston, H.D.

A number of sediment samples, collected both by coring and by grabbing, from the shallow Pacific solid waste radioactive dump site and from the Atlantic dump site, have been analyzed carefully for a number of long-lived radionuclides. Both dump sites yielded samples that were expected to serve as controls, collected at considerable distance from any visually-located waste containers, as well as other samples that were collected close to identified waste drums, some of which showed evidence of physical disintegration. The Atlantic site shows evidence of wide-spread, general contamination, with 137 Cs and possibly with 241 Am. The Pacific site is perhaps less generally contaminated with 137 Cs, but shows evidence of widespread general contamination with several transuranic nuclides. Samples collected near to identified waste containers, at both sites, show that significant portions of leached radioactivity ( 137 Cs, 239 240 Pu, 238 Pu, 241 Am, 242 Cm, and 244 Cm) are immobilized by the sediments within very short distances, possibly measured in meters or tens of meters. The data also suggest considerable differences among the horizontal trajectories of the various leached transuranic elements. It is argued that careful study of nuclide distributions around such old waste containers would provide data of great value in helping to predict long-term behavior of radionuclides released to marine environments

Behavior of nuclides at plasma melting of TRU wastes

International Nuclear Information System (INIS)

Amakawa, Tadashi; Adachi, Kazuo

2001-01-01

Arc plasma heating technique can easily be formed at super high temperature, and can carry out stable heating without any effect of physical and chemical properties of the wastes. By focussing to these characteristics, this technique was experimentally investigated on behavior of TRU nuclides when applying TRU wastes forming from reprocessing process of used fuels to melting treatment by using a mimic non-radioactive nuclide. At first, according to mechanism determining the behavior of TRU nuclides, an element (mimic nuclide) to estimate the behavior was selected. And then, to zircaloy with high melting point or steel can simulated to metal and noncombustible wastes and fly ash, the mimic nuclide was added, prior to melting by using the arc plasma heating technique. As a result, on a case of either melting sample, it was elucidated that the nuclides hardly moved into their dusts. Then, the technique seems to be applicable for melting treatment of the TRU wastes. (G.K.)

Uranium, thorium and potassium contents and radioactive equilibrium states of the uranium and thorium series nuclides in phosphate rocks and phosphate fertilizers

Energy Technology Data Exchange (ETDEWEB)

Komura, K; Yanagisawa, M; Sakurai, J; Sakanoue, M

1985-10-01

Uranium, thorium and potassium contents and radioactive equilibrium states of the uranium and thorium series nuclides have been studied for 2 phosphate rocks and 7 phosphate fertilizers. Uranium contents were found to be rather high (39-117 ppm) except for phosphate rock from Kola. The uranium series nuclides were found to be in various equilibration states, which can be grouped into following three categories. Almost in the equilibrium state, 238U approximately 230Th greater than 210Pb greater than 226Ra and 238U greater than 230Th greater than 210Pb greater than 226Ra. Thorium contents were found to be, in general, low and appreciable disequilibrium of the thorium series nuclides was not observed except one sample. Potassium contents were also very low (less than 0.3% K2O) except for complex fertilizers. Based on the present data, discussions were made for the radiation exposure due to phosphate fertilizers.

Estimate of the intensities of the radioactive nuclides produced at the super-FRS at the future GSI facility

International Nuclear Information System (INIS)

Ricciardi, M.V.

2004-11-01

The principal goal of the new facility is the construction of a worldwide unique and technically innovative accelerator system that will provide an extensive range of particle beams. Proton and antiproton beams will be available and ion beams of all chemical elements up to uranium will be produced with world-record intensities. The main employ of the high-intensity ion beams is the production of energetic beams of short-lived (radioactive) nuclei, in the following referred to as exotic or Rare Isotope Beams (RIBs). RIBs are produced in nuclear reactions experienced by the primary beams of stable particles. We report on the study of the production of radioactive nuclides and of their propagation through the Super-FRS. The study was performed by means of a nuclear-reaction Monte-Carlo code, ABRABLA, opportunely implemented for the above-described purpose. This work offers an overview of the radioactivity production in the Super-FRS area; the latter is the required starting knowledge for the design of the shielding structure. (orig.)

Radioactivity of long-lived nuclides in the primary circuit of the reactor BOR-60 during operation with defective fuel elements

International Nuclear Information System (INIS)

Gryazev, V.M.; Kizin, V.D.; Lisitsyn, E.S.; Polyakov, V.I.; Chechetkin, Y.V.

1978-06-01

The summarized results of measurements of the enrichment and distribution of radioactive nuclides from corrosion and of fission products during the four years of operation of BOR-60, including a longer period of operation with detective fuel elements in the core, are presented. It is shown that for operation with approximately 1% leaking fuel rods radiation exposure becomes worse manily because of release and enrichment of cesium isotopes in the coolant. Of the other fission products, the largest contribution to the dose rate in pipework and components is given by 140 Ba / 140 La and 95 Nb. On operation with 0.1 to 0.2% of leaking fuel rods, this contribution is comparable to that of the corrosion products 60 Co and 54 Mn. The radioactivity of corrosion products in the circuit has not increased within the last three years and was about one order of magnitude lower than the theoretical values. The corrosion and fission products are nonuniformly distributed over the circuit. Concentration of 95 Nb and 60 Co in the pipe for 'cold' sodium is larger by a factor of 2 - 5 and of 140 Ba and 54 Mn by a factor of 10-20 than in the pipes for 'hot' sodium. Most of the cobalt was found to deposit in the heat exchanges. The effectiveness of emptying the pipes from coolant in order to reduce the dose sate is assessed. (orig.) [de

The effect of radioactive aerosols on fog formation

International Nuclear Information System (INIS)

Ali, G.; Khan, E.U.; Ali, N.; Khan, H.A.; Waheed, A.

2011-01-01

This research study has been carried out to explore the dependence of fog formation on radioactive aerosols. The aerosols containing radioactive nuclides are called radioactive aerosols. A large number of radioactive nuclides are present in the atmosphere among which the two most important nuclides, 7Be and 210Pb are considered here in this study. Results for Activity Concentrations of these radio-nuclides in air samples in clear and foggy conditions were comparatively analyzed. About 19% increase in Activity concentration for 210Pb and about 23% increase in Activity Concentration for 7Be was recorded during fog as compared to clear conditions. This increase in Activity Concentration during fog indicates that the presence of aerosols laden with these radio-nuclides is also one of the so many factors responsible for fog formation

Subcellular distribution of 111In and 169Yb in tumor and liver

International Nuclear Information System (INIS)

Ando, A.; Ando, I.; Takeshita, M.; Hiraki, T.; Hisada, K.

1981-01-01

Subcellular distribution of 111 In and 169 Yb was quantitatively determined to evaluate the role of the lysosome in accumulation of these nuclides in malignant tumor tissue and in the liver using three different tumor models and the host liver. In Yoshida sarcoma and Ehrlich tumor, most of the radioactivity of these nuclides was localized in the supernatant fraction, and only a small amount of radioactivity was localized in the mitochondrial fraction, which contains lysosomes. In the liver, most of the radioactivity was concentrated in the mitochondrial fraction. The radioactivity of this fraction increased with time after the administration of these nuclides and reached approximately 50% of the total radioactivity within 24 h. In the case of hepatoma AH109A, radioactivity of the mitochondrial fraction increased with time after administration, and about 30% of the total radioactivity was concentrated in this fraction after 24 h. It is concluded that the lysosome does not play a major role in the tumor concentration of these nuclides, although it may play an important role in their liver concentration. In the case of hepatoma AH109A, it is pressumed that lysosome plays a considerably important role in the tumor concentration of these nuclides, hepatoma AH109A possessing some residual features of the liver. (orig.)

Cosmic-ray produced nuclides in ground level air and in precipitation

Energy Technology Data Exchange (ETDEWEB)

Schumann, G.; Roedel, W.; Stoeppler, M.

1963-11-15

There are mainly three kinds of radioactive substances in the atmosphere: emanations from the ground and their daughters, nuclides produced in the atmosphere by cosmic rays, and artificial products originating from nuclear weapon tests (and in a very small amount from other nuclear technical applications). This paper deals in particular with some of the cosmic-ray produced nuclides.

Physics with radioactive nuclear beams

International Nuclear Information System (INIS)

Boyd, R.N.; Tanihata, I.

1992-01-01

Recently developed facilities allow a wide range of new investigations of the reactions and properties of short-lived nuclei. These studies may help to solve puzzles of nuclear structure and the Big Bang. The purpose of nuclear physics is to measure properties of specific nuclides and infer from them global properties common to all nuclides. One goal, for example, is to understand nuclear sizes and matter distributions in terms of basic nuclear forces. Another is to understand the variation throughout the periodic table of the dominant quantum states, which are known as the open-quotes nuclear shell modelclose quotes states and are characterized, much as are atomic states, by a principal quantum number and by orbital and total angular momentum quantum numbers. In turn other nuclear phenomena, such as the collective excitations known as giant resonances, can be understood in terms of the shell-model configurations and basic nuclear parameters. Radioactive nuclear beam studies of reactions of short-lived nuclides have already yielded results with important ramifications in both nuclear physics and astrophysics. Nuclear physicists expect unstable nuclides to exhibit unusual structures or features that may test their understanding of known nuclear phenomena at extreme conditions, and perhaps even to reveal previously unknown nuclear phenomena, Astrophysicists, for their part, have known for several decades that processes in both Big Bang nucleosynthesis and stellar nucleosynthesis involve short-lived nuclides. Indeed, the original motivation for developing radioactive nuclear beams was astrophysical. 25 refs., 7 figs

Physics with radioactive nuclear beams

International Nuclear Information System (INIS)

Boyd, R.N.

1995-01-01

Recently developed facilities allow a wide range of new investigations of the reactions and properties of short-lived nuclei. These studies may help to solve puzzles of nuclear structure and the Big Bang. The purpose of nuclear physics is to measure properties of specific nuclides and infer from them global properties common to all nuclides, for example, is to understand nuclear sizes and matter distributions in terms of basic nuclear forces. Another is to understand the variation throughout the periodic table of the dominant quantum states, which are known as the open-quotes nuclear shell model close quotes states and are characterized, much as are atomic states, by a principal quantum number and by orbital and total angular momentum quantum numbers. In turn other nuclear phenomena, such as the collective excitations known as giant resonances, can be understood in terms of the shell-model configurations and basic nuclear parameters. Radioactive nuclear beam studies of reactions of short-lived nuclides have already yielded results with important ramifications in both nuclear physics and astrophysics. Nuclear physicists expect unstable nuclides to exhibit unusual structures or features that may test their understanding of known nuclear phenomena at extreme conditions, and perhaps even to reveal previously unknown nuclear phenomena, Astrophysicists, for their part, have known for several decades that processes in both Big Bang nucleosynthesis and stellar nucleosynthesis involve short-lived nuclides. Indeed, the original motivation for developing radioactive nuclear beams was astrophysical. (author). 25 refs., 7 figs

A GoldSim Model for Colloid Facilitated Nuclide Transport

International Nuclear Information System (INIS)

Lee, Youn Myoung; Jeong, Jong Tae

2010-01-01

Recently several total system performance assessment (TSPA) programs, called 'template' programs, ready for the safety assessment of radioactive waste repository systems which are conceptually modeled have been developed by utilizing GoldSim and AMBER at KAERI. It is generally believed that chelating agents (chelators) that could be disposed of together with radioactive wastes in the repository and natural colloids available in the geological media affect on nuclides by enhancing their transport in the geological media. A simple GoldSim module to evaluate such quantitative effects, by which colloid and chelator-facilitated nuclide release cases could be modeled and evaluated is introduced. Effects of the chelators alone are illustrated with the case associated with well pumping scenario in a hypothetical repository system

Alpha-emitting nuclides in the marine environment

Science.gov (United States)

Pentreath, R. J.

1984-06-01

The occurrence of alpha-emitting nuclides and their daughter products in the marine environment continues to be a subject of study for many reasons. Those nuclides which occur naturally, in the uranium, thorium and actinium series, are of interest because of their value in determining the rates of geological and geochemical processes in the oceans. Studies of them address such problems as the determination of rates of transfer of particulate matter, deposition rates, bioturbation rates, and so on. Two of the natural alpha-series nuclides in which a different interest has been expressed are 210Po and 226Ra, because their concentrations in marine organisms are such that they contribute to a significant fraction of the background dose rates sustained both by the organisms themselves and by consumers of marine fish and shellfish. To this pool of naturally-occurring nuclides, human activities have added the transuranium nuclides, both from the atmospheric testing of nuclear devices and from the authorized discharges of radioactive wastes into coastal waters and the deep sea. Studies have therefore been made to understand the chemistry of these radionuclides in sea water, their association with sedimentary materials, and their accumulation by marine organisms, the last of these being of particular interest because the transuranics are essentially "novel" elements to the marine fauna and flora. The need to predict the long-term behaviour of these nuclides has, in turn, stimulated research on those naturally-occurring nuclides which may behave in a similar manner.

Spectrometry techniques for radioactivity measurements

International Nuclear Information System (INIS)

Anilkumar, S.

2016-01-01

The energy of the radiation emission following the nuclear decay is unique and the characteristic of the radio nuclide which undergoes decay. Thus measurement of the energy of the radiation offers a method of identifying the radio nuclides. The prime requirement of the energy measurement is a suitable detector which shows response proportional to the energy of the radiation rather than the presence of the radiation. The response from such detectors are suitably processed and distributed with respect to the signal strength which is proportional to incident energy. This distribution is normally referred as energy spectrum and is recorded in the multichannel analyser. The measurement of energy and intensity of radiation from the spectrum is called radiation spectrometry. Thus the radiation spectrometry allows the identification and quantification of radioactive isotopes in variety of matrices. The radiation spectrometry has now become a popular radioanalytical technique in wide area of nuclear fuel cycle programs. The popular spectrometry techniques commonly used for the radioactivity measurement and analysis are Alpha spectrometry, Gamma ray spectrometry and Beta spectrometry

Natural radioactivity of bedrock bath instruments and hot spring instruments in Japan

International Nuclear Information System (INIS)

Kazuki Iwaoka; Hiroyuki Tabe; Hidenori Yonehara

2013-01-01

In Japan, bedrock bath instruments and hot spring instruments that contain natural radioactive nuclides are commercially available. In this study, such instruments containing natural radioactive nuclides, currently distributed in Japan, were collected and the radioactivity concentration of 238 U series, 232 Th series, and 40 K in them was determined by gamma ray spectrum analyses. Effective doses to workers and general consumers handling the materials were estimated, revealing the radioactivity concentration of 238 U series, 232 Th series, and 40 K to be lower than critical values given in the IAEA Safety Guide. The maximum effective doses to workers and general consumers were 210 and 6.1 μSv y -1 , respectively. These values are lower than the intervention exemption level (1,000 μSv y -1 ) given in ICRP Publ. 82. (author)

Final results of the 'Benchmark on computer simulation of radioactive nuclides production rate and heat generation rate in a spallation target'

International Nuclear Information System (INIS)

Janczyszyn, J.; Pohorecki, W.; Domanska, G.; Maiorino, R.J.; David, J.C.; Velarde, F.A.

2011-01-01

A benchmark has been organized to assess the computer simulation of nuclide production and heat generation in a spallation lead target. The physical models applied for the calculation of thick lead target activation do not produce satisfactory results for the majority of analysed nuclides, however one can observe better or worse quantitative compliance with the experimental results. Analysis of the quality of calculated results show the best performance for heavy nuclides (A: 170 - 190). For intermediate nuclides (A: 60 - 130) almost all are underestimated while for A: 130 - 170 mainly overestimated. The shape of the activity distribution in the target is well reproduced in calculations by all models but the numerical comparison shows similar performance as for the whole target. The Isabel model yields best results. As for the whole target heating rate, the results from all participants are consistent. Only small differences are observed between results from physical models. As for the heating distribution in the target it looks not quite similar. The quantitative comparison of the distributions yielded by different spallation reaction models shows for the major part of the target no serious differences - generally below 10%. However, in the most outside parts of the target front layers and the part of the target at its end behind the primary protons range, a spread higher than 40 % is obtained

Subcellular distribution of /sup 111/In and /sup 169/Yb in tumor and liver

Energy Technology Data Exchange (ETDEWEB)

Ando, A; Ando, I; Takeshita, M; Hiraki, T; Hisada, K

1981-05-01

Subcellular distribution of /sup 111/In and /sup 169/Yb was quantitatively determined to evaluate the role of the lysosome in accumulation of these nuclides in malignant tumor tissue and in the liver using three different tumor models and the host liver. In Yoshida sarcoma and Ehrlich tumor, most of the radioactivity of these nuclides was localized in the supernatant fraction, and only a small amount of radioactivity was localized in the mitochondrial fraction, which contains lysosomes. In the liver, most of the radioactivity was concentrated in the mitochondrial fraction. The radioactivity of this fraction increased with time after the administration of these nuclides and reached approximately 50% of the total radioactivity within 24 h. In the case of hepatoma AH109A, radioactivity of the mitochondrial fraction increased with time after administration, and about 30% of the total radioactivity was concentrated in this fraction after 24 h. It is concluded that the lysosome does not play a major role in the tumor concentration of these nuclides, although it may play an important role in their liver concentration. In the case of hepatoma AH109A, it is pressumed that lysosome plays a considerably important role in the tumor concentration of these nuclides, hepatoma AH109A possessing some residual features of the liver.

Nuclide-specific monitoring of airborne radioactivity

International Nuclear Information System (INIS)

Aures, R.; Neu, A.

1996-01-01

Since the end of the seventies the Landesanstalt fuer Umweltschutz Baden-Wuerttemberg ist operating two radioaerosol monitoring stations at the border in the opposite of foreign nuclear power plants. Since the end of the eighties six similar monitoring stations were built up for measuring activity in breathing air in the common environment in Baden-Wuerttemberg. A special filtersystem allows measuring the activity concentration of up to 99 nuclides. The measuring system was optimized by advanced PC-technology, a multitasking operating system and a special software for users and gamma-spectroscopy. These increased the average availability of all monitoring stations to 96% in 1996. (orig.) [de

The production of residual nuclides in Pb irradiated by 400 MeV/u carbon ions

Energy Technology Data Exchange (ETDEWEB)

Ge, H.L. [Institute of Modern Physics, Chinese Academy of Sciences, Lanzhou 730000 (China); Ma, F., E-mail: mf@impcas.ac.cn [Institute of Modern Physics, Chinese Academy of Sciences, Lanzhou 730000 (China); Zhang, X.Y.; Ju, Y.Q.; Zhang, H.B.; Chen, L.; Luo, P. [Institute of Modern Physics, Chinese Academy of Sciences, Lanzhou 730000 (China); Zhou, B. [Institute of High Energy Physics, Chinese Academy of Sciences, Beijing 100049 (China); Zhang, Y.B.; Li, J.Y.; Xu, J.K. [Institute of Modern Physics, Chinese Academy of Sciences, Lanzhou 730000 (China); Liang, T.J. [Institute of Physics, Chinese Academy of Sciences, Beijing 100190 (China); Wang, S.L. [Institute of High Energy Physics, Chinese Academy of Sciences, Beijing 100049 (China); Yang, Y.W.; Yang, L. [Institute of Modern Physics, Chinese Academy of Sciences, Lanzhou 730000 (China)

2014-10-15

The experiment was performed by irradiating a Pb foil with 400 MeV/u carbon beam at the HIRFL-CSR in Lanzhou, China. The experimental data was acquired by the off-line γ-spectroscopy method. 32 radioactive residual nuclides had been observed and their cross sections were determined. The measured results were compared with the results simulated by Monte Carlo code MCNPX2.7.0. The comparison shows that the simulated cross sections were underestimated for the fragments from A = 20 to 41 and A = 110 to 175. By fitting the measured and simulated cross sections to Rudstams semi-empirical formula, it was found that the charge distribution of products was asymmetric for the residual nuclides with a high mass number.

Measurement of radioactivity in steel

International Nuclear Information System (INIS)

Wachtendonk, H.-J. von; Luengen, S.; Wilke, N.

1999-01-01

Even after the control of scrap deliveries, there remains a small risk that the radioactive contaminated scrap passes the detecting devices. Therefore, the chemical laboratory takes a role to measure each heat for the absence of artificial radioactive nuclides with a gamma spectrometer equipped with NaI-detector. As the measurement must be performed in sequence with the steel production process, the allowable time for the measurement is quite limited. On the other hand, there could be still some possibility that background radiation might be present as the samples may contain some natural radioactivity. The task is how to differentiate the nature of radioactivity between naturally remaining radioactivity within safe limit and artificial nuclides present in the sample at a low level even though a very small amount of radioactivity could be detected in short time in both cases. We have set the alarm limit to 0.1 Bq/g for Co-60 as indicating nuclide. This limit is set more than 4 s (s = standard deviation) from the average background radiation. Therefore, false alarms are quite improbable. Strategy: The NaI gamma spectrometer performs a gross gamma measurement but it can not differentiate the nature of the nuclides present. If the alarm limit is hurt, the sample is measured on a high resolution gamma spectrometer with Ge-detector for identification of the gamma emitting nuclides. Calibration: Even though no appropriate international standards are adapted and no commercial measuring equipment is commercially available, the desired standard should contain Co-60 in the order of 1 to 100 Bq/g. The presence of other gamma emitting nuclides is desirable. In the Workshop we will present how to surmount this difficulty. (author)

Validation of spent nuclear fuel nuclide composition data using percentage differences and detailed analysis

Energy Technology Data Exchange (ETDEWEB)

Kim, Man Cheol [Chung-Ang Univ., Seoul (Korea, Republic of). School of Energy Systems Engineering

2017-06-15

Nuclide composition data of spent nuclear fuels are important in many nuclear engineering applications. In reactor physics, nuclear reactor design requires the nuclide composition and the corresponding cross sections. In analyzing the radiological health effects of a severe accident on the public and the environment, the nuclide composition in the reactor inventory is among the important input data. Nuclide composition data need to be provided to analyze the possible environmental effects of a spent nuclear fuel repository. They will also be the basis for identifying the origin of unidentified spent nuclear fuels or radioactive materials.

IDGAM. A PC code and database to help nuclide identification in activation analysis

International Nuclear Information System (INIS)

Paviotti Corcuera, R.; Moraes Cunha, M. de; Jayanthi, K.A.

1994-01-01

The document describes a PC diskette containing a code and database which helps researchers to identify the nuclides in a radioactive sample. Data can be retrieved by gamma-ray energy, nuclide or element. The PC diskette is available, costfree, from the IAEA Nuclear Data Section, upon request. (author). 6 refs, 5 figs

Spatial distribution sampling and Monte Carlo simulation of radioactive isotopes

CERN Document Server

Krainer, Alexander Michael

2015-01-01

This work focuses on the implementation of a program for random sampling of uniformly spatially distributed isotopes for Monte Carlo particle simulations and in specific FLUKA. With FLUKA it is possible to calculate the radio nuclide production in high energy fields. The decay of these nuclide, and therefore the resulting radiation field, however can only be simulated in the same geometry. This works gives the tool to simulate the decay of the produced nuclide in other geometries. With that the radiation field from an irradiated object can be simulated in arbitrary environments. The sampling of isotope mixtures was tested by simulating a 50/50 mixture of $Cs^{137}$ and $Co^{60}$. These isotopes are both well known and provide therefore a first reliable benchmark in that respect. The sampling of uniformly distributed coordinates was tested using the histogram test for various spatial distributions. The advantages and disadvantages of the program compared to standard methods are demonstrated in the real life ca...

Survey monitoring of environmental radioactivity in Busan area

Energy Technology Data Exchange (ETDEWEB)

Yang, H. S.; Lee, J. [Busan Regional Monitoring Station, Busan (Korea, Republic of)

2000-12-15

At Pusan Regional Monitoring Station in Busan have been measured periodically in 2000 gross beta activities in the airborne dust, fallout, precipitation and tap water and gamma exposure rates. Gamma nuclides in airborne dust, fallout and precipitation have also been monitored at the station. As a part of environmental radiation/radioactivity distribution survey around Pusan, vegetables, fishes, shellfish, drinking water (total 23ea) samples were taken from sampling sites which were selected by KlNS. We analysis gamma nuclide for all. No significant changes from the previous survey have been found in both beta activities and gamma exposure rates. As the results of analyzing an gamma nuclide concentration in environmental samples in Pusan are fee of radiological contaminants.

Nuclide inventories of spent fuels from light water reactors

International Nuclear Information System (INIS)

Okumura, Keisuke; Okamoto, Tsutomu

2012-02-01

Accurate information on nuclide inventories of spent fuels from Light Water Reactors (LWRs) is important for evaluations of criticality, decay heat, radioactivity, toxicity, and so on, in the safety assessments of storage, transportation, reprocessing and waste disposal of the spent fuels. So, a lot of lattice burn-up calculations were carried out for the possible fuel specifications and irradiation conditions in Japanese commercial LWRs by using the latest nuclear data library JENDL-4.0 and a sophisticated lattice burn-up calculation code MOSRA-SRAC. As a result, burn-up changes of nuclide inventories and their possible ranges were clarified for 21 heavy nuclides and 118 fission products, which are important from the viewpoint of impacts to nuclear characteristics and nuclear fuel cycle and environment. (author)

Analytical method for solving radioactive transformations

International Nuclear Information System (INIS)

Vudakin, Z.

1999-01-01

Analytical method for solving radioactive transformations is presented in this paper. High accuracy series expansion of the depletion function and nonsingular Bateman coefficients are used to overcome numerical difficulties when applying well-known Bateman solution of a simple radioactive decay. Generality and simplicity of the method are found to be useful in evaluating nuclide chains with one hundred or more nuclides in the chain. Method enables evaluation of complete chain, without elimination of short-lives nuclides. It is efficient and accurate

Nuclide transfer test device in soil

International Nuclear Information System (INIS)

Sakata, Yoshiyuki.

1994-01-01

The device comprises a pressure-proof vessel having a perforated port, a compression vessel having a sample-containing chamber with circumferential walls having a plurality of small holes being gastightly engaged to the perforated port, a mechanically pressurizing means for vertically compressing the compression chamber, a pressurizing gas supply system for supplying a pressurizing gas to compress the soil specimen in a lateral direction and a sample water-supply system for supplying sample water to the sample containing chamber. The soil sample is pressurized so that the sample water is caused to permeate by isotropic pressure due to equilibrium of vertical compression by mechanical force and lateral compression by the pressurizing gas. The transfer state of radioactive nuclides in the soil can be tested easily in a state where the sample water is caused to permeate in a vertical direction in parallel, to simulate an actual processing circumstance. Namely, since the sample water is caused to permeate to the soil sample in the pressure-proof vessel, a desired test can easily be conducted in a restricted space without undergoing influences of the kind and the dose rate of the radioactive nuclides. (N.H.)

Removal of Radioactive Nuclides by Multi-Functional Microcapsules Enclosing Inorganic Ion-Exchangers and Organic Extractants

Energy Technology Data Exchange (ETDEWEB)

Mimura, H.; Akiba, K.; Onodera, Y.

2002-02-26

The microcapsules enclosing two kinds of functional materials, inorganic ion-exchangers and organic extractants, were prepared by taking advantage of the high immobilization ability of alginate gel polymer. The fine powders of inorganic ion-exchanger and oil drops of extractant were kneaded with sodium alginate (NaALG) solution and the kneaded sol readily gelled in a salt solution of CaCl2, BaCl2 or HCl to form spherical gel particles. The uptake properties of various nuclides, 137Cs, 85Sr, 60Co, 88Y, 152Eu and 241Am, for thirty-four specimens of microcapsules in the presence of 10-1-10-4 M HNO3 were evaluated by the batch method. The distribution coefficient (Kd) of Cs+ above 103 cm3/g was obtained for the microcapsules enclosing CuFC or AMP. The Kd of Sr2+ around 102 cm3/g was obtained for the microcapsules containing clinoptilolite, antimonic acid, zeolite A, zeolite X or titanic acid. The microcapsules enclosing DEHPA exhibited relatively large Kd values of trivalent metal ions above 103 cm3/g; for example, the Kd values of Cs+, Sr2+, Co2+, Y3+, Eu3+ and Am3+ for a favorable microcapsule (CuFC/clinoptilolite/DEHPA/CaALG) were 1.1x104, 7.5x10, 1.1x10, 1.0x104, 1.4x104, 3.4x103 cm3/g, respectively. The uptake rates of Cs+, Y3+, Eu3+ and Am3+ for this microcapsule were rather fast; the uptake percentage above 90% was obtained after 19 h-shaking and the uptake equilibrium was attained within 1 d. The AMP/CaALG exhibited high uptake ability for Cs+ even after irradiation of 188 kGy, and DEHPA/CaALG microcapsule had similar Kd values of Cs+, Sr2+, Co2+, Y3+, Eu3+ and Am3+ ions before and after irradiation. The microcapsules with various shapes such as spherical, columnar, fibrous and filmy forms were easily prepared by changing the way of dipping kneaded sol into gelling salt solution. The microcapsules enclosing inorganic ion-exchangers and extractants have a potential possibility for the simultaneous removal of various radioactive nuclides from waste solutions.

Terms and definitions in the field of radiological technique. Radioactivity. Draft. Begriffe und Benennungen in der radiologischen Technik. Radioaktivitaet. Entwurf

Energy Technology Data Exchange (ETDEWEB)

1978-04-01

Nuclides and their symbols: Nuclide, symbol for nuclides; Nuclear processes: Nuclear transformation, isomeric transition; Radioactive substances; Radiation of radioactive substances: Alpha radiation, beta radiation, k radiation, gamma radiation, conversion electrons, annihilation radiation, neutron radiation; Activity, specific activity, and activity concentration; Characteristic constants of radio nuclides: Decay constant, lifetime, half-life, specific gamma-ray constant, conversion coefficient; Decay series: Radioactive decay series, radioactive equilibrium; Nuclides with special names and symbols: Hydrogen isotopes, nuclides of the natural decay series.

The terrestrial environmental dynamics of radioactive nuclides released by the Fukushima nuclear accident

International Nuclear Information System (INIS)

Furukawa, Jun

2014-01-01

Research into environmental dynamics of radioactive nuclides released by the Fukushima nuclear accident, especially radiocesium 137 Cs (half-life, 30.1 years), is highly focused especially on diffusion processes of radiocesium into ecosystems, which is high-priority knowledge. Because of relatively sparse knowledge about the reallocation of radiocesium contained in organic matter in terrestrial ecosystems, the effects of diffused rediocesium into ecosystem cannot be accurately estimated. In this article, the terrestrial environmental dynamics of radiocesium mainly in the processes of plant uptake and the possibility of release from plants will be discussed. Plants uptake minerals from soil and these minerals are likewise ingested by animals that feed on plants, including humans. Therefore one of the main gateways of radiocesium into ecosystem is via plants. From the viewpoint of human dietary consumption, rice contamination with radiocesium has been energetically investigated and useful data are accumulating. Processes of radiocesium uptake mechanisms by plants are being researched using legumes, e.g. soybean. Speculation on the possibility of radiocesium release into forest atmosphere via plant activity will be introduced. (author)

Radioactive aerosols

International Nuclear Information System (INIS)

Chamberlain, A.C.

1991-01-01

Radon. Fission product aerosols. Radioiodine. Tritium. Plutonium. Mass transfer of radioactive vapours and aerosols. Studies with radioactive particles and human subjects. Index. This paper explores the environmental and health aspects of radioactive aerosols. Covers radioactive nuclides of potential concern to public health and applications to the study of boundary layer transport. Contains bibliographic references. Suitable for environmental chemistry collections in academic and research libraries

Radioactive certified reference materials

International Nuclear Information System (INIS)

Watanabe, Kazuo

2010-01-01

Outline of radioactive certified reference materials (CRM) for the analysis of nuclear materials and radioactive nuclides were described. The nuclear fuel CRMs are supplied by the three institutes: NBL in the US, CETAMA in France and IRMM in Belgium. For the RI CRMs, the Japan Radioisotope Association is engaged in activities concerning supply. The natural-matrix CRMs for the analysis of trace levels of radio-nuclides are prepared and supplied by NIST in the US and the IAEA. (author)

Preparation of radioactive tracer for studying sediment movement

International Nuclear Information System (INIS)

Hussain, S.D.; Ghauri, G.A.; Qureshi, M.H.; Khan, N.A.

1983-06-01

In order to study the movement of sediment in harbours, estuaries and streams, artificial sediment in the form of glass is prepared. A preselected nuclide is added to the glass during its manufacture. The density and size distribution of the glass particles is method with that of the natural sediment. The activation of the artificial sediment in a reactor changes the nuclide into a radioactive isotope thereby tagging it and making it possible to trace its movement with suitable radiation detector. The method of tracer preparation is described with special reference to sadiment movement studies at Karachi harbour. (authors)

Modelling indoor exposure to natural radioactive nuclides

International Nuclear Information System (INIS)

Hofmann, W.; Daschil, F.

1986-01-01

Radon enters buildings from several sources primarily from building materials and from the soil or rocks that underlie or surround building fundaments. A multicompartment model was developed which describes the fate of radon and attached or free radon decay products in a model room by a set of linear time-dependent differential equations. Time-dependent coefficients allow to model temporal parameter changes, e.g. the opening of windows, or a sudden pressure drop leading to enhanced exhalation. While steady-state models were used to study the effect of parameter changes on steady state nuclide concentrations, the time-dependent models provided additional information on the time scale of these changes. (author)

IVO's nuclide removal system takes to the road

International Nuclear Information System (INIS)

Tusa, E.H.

1995-01-01

The successful and routine use of IVO's treatment system for the removal of cesium from the evaporator concentrates at the Loviisa WER plant in Finland is described. The system uses a granular inorganic hexacyanoferate-based ion exchanger to separate cesium from liquid radioactive wastes. The compactness of the original systems at Loviisa suggested the development of a transportable unit. A combined nuclide removal system was created which included a highly efficient ultrafiltration unit to separate nearly all particulate material carrying radionuclides, as well as the cesium removal capability. A 20ft long container carrying the removal package was completed in 1994. This NUclide REmoval System (NURES) was used for the first time in January 1995 to purify liquid waste accumulating at training reactors in Estonia and has performed well. As an extension of nuclide removal, a process has been created to recover boron from liquid wastes. A system for boron recovery and nuclide removal has been designed for use at the Paks plant in Hungary. The removal process has been shown to improve the safety of final waste disposal compared with the alternative treatment by cementation because the cesium is very tightly bound into the ion exchange material. (UK)

Distribution of transuranic nuclides in Mediterranean ecosystems

International Nuclear Information System (INIS)

Ballestra, S.; Thein, M.; Fukai, R.

1982-01-01

For the comprehensive understanding of the behaviour of transuranic elements in the marine environment, the knowledge on the distribution of these elements in various components of marine ecosystems is essential. Since the Mediterranean Sea is considered a sufficiently self-contained system, our approach for studying the processes controlling the transuranic cycling in the sea has been to follow, step by step, the redistribution of plutonium and americium in different components of the marine environment, taking Mediterranean ecosystems as examples. While the studies in the past years have supplied quantitative information on the inputs of plutonium and americium into the Mediterranean from atmospheric fallout and rivers as well as on their behaviour in the Mediterranean water column, only scattered data have been made available so far on the occurrence of the transuranic nuclides in the Mediterranean marine biota or sediments. In order to fill up this information gap, biological and sediment samples were collected from the northwestern Mediterranean region during 1975-1978 for the transuranic measurements. The results of these determinations are given in the present report

Influence of Groundwater Flow Rate on Nuclide Releases from Pyro-processed Waste Repository

International Nuclear Information System (INIS)

Lee, Youn Myoung; Jeong, Jong Tae

2011-01-01

Since the early 2000s several template programs for the safety assessment of a high-level radioactive waste repository as well as a low- and intermediate level radioactive waste repository systems have been developed by utilizing GoldSim and AMBER at KAERI. Very recently, another template program for a conceptual hybrid-typed repository system, called 'A-KRS' in which two kinds of pyroprocessed radioactive wastes, low-level metal wastes and ceramic high-level wastes that arise from pyroprocessing of PWR nuclear spent fuels has been developed and are to be disposed of by separate disposal strategies. The A-KRS is considered to be constructed at two different depths in geological media: 200m depth, at which a possible human intrusion is considered to be limited after closure, for the pyroprocessed metal wastes with lower or no decay heat producing nuclides, and 500m depth, believed to be in the reducing condition for nuclides with a rather higher radioactivity and heat generation rate. This program is ready for total system performance assessment which is able to evaluate nuclide release from the repository and farther transport into the geosphere and biosphere under various normal, disruptive natural and manmade events, and scenarios that can occur after a failure of waste package and canister. To quantify a nuclide release and transport through the possible various pathways especially in the near-fields of the A-KRS repository system, some illustrative evaluations have been made through the study. Even though all parameter values associated with the A-KRS were assumed for the time being, the illustrative results should be informative since the evaluation of such releases is very important not only in view of the safety assessment of the repository, but also for design feedback of its performance

Status of determining transuranic nuclides speciation in aqueous solution with laser spectrometry

International Nuclear Information System (INIS)

Wang Bo; Liu Dejun; Yao Jun; Chen Xi; Long Haoqi; Zeng Jishu; Su Xiguang; Fan Xianhua

2007-01-01

The knowledge about speciation of transuranic nuclides in aqueous solution is a basis for understanding the chemical and migration behavior of transuranic nuclides in aqueous solution. The speciation of transuranic nuclides with trace concentration is complicated in near neutral aqueous solutions, including change of oxidation state, complexation and colloid generation, etc. The concentrations of transuranium in near neutral aqueous solution usually below the sensitivity range of method such as conventional absorption spectroscopy. The radioactive analysis method has a very low detection limits for radionuclides, however, it wouldn' t allow the direct measurement of the transuranic species. In contrast with these methods, laser spectroscopy is an ideal method with high sensitivity, and non-contact and non-destructive for determining the speciation of transuranic nuclides. This paper summarizes the status and application of LIPAS (Laser-induced Photoacoustic Spectrometry), LIBD (Laser-induced Breakdown Detection) and TRLFS (Time-resolved Laser Fluorescence Spectrometry) to determine the speciation of transuranic nuclides with trace concentration in aqueous solutions. (authors)

Radioactive waste processing device

International Nuclear Information System (INIS)

Seki, Shuji.

1992-01-01

Liquid wastes are supplied to a ceramic filter to conduct filtration. In this case, a device for adding a powdery inorganic ion exchanger is disposed to the upstream of the ceramic filter. When the powdery inorganic ion exchanger is charged to the addition device, it is precoated to the surface of the ceramic filter, to conduct separation of suspended matters and separation of ionic nuclides simultaneously. Liquid wastes returned to a collecting tank are condensed while being circulated between the ceramic filter and the tank and then contained in a condensation liquid waste tank. With such a constitution, both of radioactive nuclides accompanied by suspended matters in the radioactive liquid wastes and ionic nuclides can be captured efficiently. (T.M.)

Systematic analysis method for radioactive wastes generated from nuclear research facilities

International Nuclear Information System (INIS)

Kameo, Yutaka; Ishimori, Ken-ichiro; Haraga, Tomoko; Shimada, Asako; Katayama, Atsushi; Nakashima, Mikio; Takahashi, Kuniaki

2011-01-01

Analytical methods have been developed for the simple and rapid determination of radioactive nuclides, which are selected as important nuclides for the safety assessment of the disposal of wastes generated from research facilities. We advanced the development of a high-efficiency nondestructive measurement technique for γ-ray-emitting nuclides, simple and rapid methods for the pretreatment of hard-to-dissolve samples and subsequent radiochemical separation, and rapid determination methods for long-lived nuclides. In order to establish a system to analyze the important nuclides in various kinds of sample, actual radioactive wastes such as concentrated liquid waste, activated concrete, and metal pipes were analyzed by the present method. The results showed that the present method was well suited for a rapid and simple determination of low-level radioactive wastes generated from research facilities. (author)

Induced fission track distribution from highly radioactive particles in fallout materials

International Nuclear Information System (INIS)

Hashimoto, Tetsuo; Okada, Tatemichi

1987-01-01

Some highly radioactive fallout particles (GPs) from the 19th Chinese nuclear detonation were followed to the neutron irradiation in a reactor after sandwiched with mica detectors. The interesting star-like fission track patterns were revealed on the etched surface of the mica detectors. The simple chemical separation procedure for the GPs was applied for the separation of U and Pu as fissile elements and the both resultant fractions were examined with the similar high sensitive fission tracking detection. Subsequently, a representative track pattern from a black spherical particle was subjected to the determination of fissile nuclide content; comparing the total fission events evaluated on the basis of the numerical calculation of track densities with the total thermal neutron fluence. The results implied that the uranium is responsible for the main fissile nuclide remaining within a particle as unfissioned fractions and should be certainly enriched with respect to U-235 within such small fallout particles. This sophisticated method was also applied to determine the dead GPs, which have been highly radioactive particles just after the detonations, in the rain and snow-residual materials. Many induced star-like fission tracks verified certainly that there remains a lot of dead particles in the atmosheric environment till nowadays. (author)

Block scale interpretation on the spatial distribution of the fracture system in the study sites

Energy Technology Data Exchange (ETDEWEB)

Kim, Kyung Su; Bae, Dae Seok; Kim, Chun Soo; Koh, Yong Kweon; Kim, Geon Young [Korea Atomic Energy Research Institute, Taejeon (Korea)

2002-05-01

The safety of waste disposal can be achieved by a complete isolation of radioactive wastes from biosphere or by a retardation of nuclide migration to reach an acceptable dose level. For the deep geological disposal of high-level radioactive waste, the potential pathways of nuclide primarily depend on the spatial distribution characteristics of conductive fractures in rock mass. This study aims to characterize the spatial distribution characteristics of regional lineaments and background fracture system in eastern and western-type granite rock mass. The spatial distribution characteristics of the fracture system around 500m depth has been estimated based on the homogeneous discontinuity domain except for the highly fractured upper zone. 6 refs., 16 figs., 7 tabs. (Author)

Map of calculated radioactivity of fission product, 3

International Nuclear Information System (INIS)

Takeda, Tsuneo

1977-02-01

In this work, the radioactivities of fission products were calculated and summarized in contour maps and tables depending on irradiation and cooling times. The irradiation condition and other parameters used for the present calculation are shown in the followings. Neutron flux (N sub(th)): 3x10 13 n/sec/cm 2 Atom number of uranium: 1 mole (6x10 23 , ca. 271 gUO 2 ) Enrichment of U-235: 2.7% Range of irradiation time: 60-6x10 7 sec (ca. 1.9 y) Range of cooling time: 60-6x10 7 sec (ca. 1.9 y). Values of the neutron flux and the enrichment treated here are representative for common LWRs. The maps and tables of 560 nuclides are divided and compiled into the following three volumes. Vol. I: Maps of radioactivity of overall total, element total and each nuclide (Ni - Zr), Vol. II: Maps of radioactivity of each nuclide (Nb - Sb), Vol. III: Maps of radioactivity of each nuclide (Te - Tm). (auth.)

Map of calculated radioactivity of fission product, (1)

International Nuclear Information System (INIS)

Takeda, Tsuneo

1977-02-01

In this work, the radioactivities of fission products were calculated and summarized in contour maps and tables depending on irradiation and cooling times. The irradiation condition and other parameters used for the present calculation are shown in the followings. Neutron flux (N sub(th)): 3x10 13 n/sec/cm 2 Atom number of uranium: 1 mole (6x10 23 , ca. 271 gUO 2 ) Enrichment of U-235: 2.7% Range of irradiation time: 60-6x10 7 sec (ca. 1.9 y) Range of cooling time: 60-6x10 7 sec (ca. 1.9 y). Values of the neutron flux and the enrichment treated here are representative for common LWRs. The maps and tables of 560 nuclides are divided and compiled into the following three volumes. Vol. I Maps of radioactivity of overall total, element total and each nuclide (Ni - Zr) Vol. II Maps of radioactivity of each nuclide (Nb - Sb) Vol. III Maps of radioactivity of each nuclide (Te - Tm) (auth.)

Map of calculated radioactivity of fission product, 2

International Nuclear Information System (INIS)

Takeda, Tsuneo

1977-02-01

In this work, the radioactivities of fission products were calculated and summarized in contour maps and tables depending on irradiation and cooling times. The irradiation condition and other parameters used for the present calculation are shown in the followings. Neutron flux (N sub(th)): 3x10 13 n/sec/cm 2 Atom number of uranium: 1 mole (6x10 23 , ca. 271 gUO 2 ) Enrichment of U-235: 2.7% Range of irradiation time: 60-6x10 7 sec (ca. 1.9 y) Range of cooling time: 60-6x10 7 sec (ca. 1.9 y). Values of the neutron flux and the enrichment treated here are representative for common LWRs. The maps and tables of 560 nuclides are divided and compiled into the following three volumes. Vol. I: Maps of radioactivity of overall total, element total and each nuclide (Ni - Zr), Vol. II: Maps of radioactivity of each nuclide (Nb - Sb), Vol. III: Maps of radioactivity of each nuclide (Te - Tm). (auth.)

Various problems concerning radioactive waste disposal sites and parameters for their evaluation

International Nuclear Information System (INIS)

Fukui, Masami

1990-01-01

The present report first describes various methods used for low-level radioactive waste disposal in the U.S. and then discusses major factors affecting the parameters used for quantitative evaluation of the behavior of radioactive nuclides existing in the environment, focusing on the distribution coefficient which is assumed in a model widely used for such evaluation. Some problems encountered in applying these parameters to practical evaluation are also discussed together with further studies required in the future. The distribution coefficient varies with many physical, chemical and biological factors, and it may be unavoidable to rely on experiments with a simplified system in determining the effect of each factor separately. However, the values obtained from such experiments cannot be used as parameters to reflect the behaviors of these nuclides in real environments. They should be considered as such. Efforts should be made to develop techniques to obtain effective values for the distribution coefficient that properly reflect their behaviors in real environments near disposal sites or in far fields. (N.K.)

Difficulty in the usage of nuclides in hospitals

International Nuclear Information System (INIS)

Ueda, Hideo

1980-01-01

In Japan, the uses of radioisotopes in hospitals are increasing year after year. Therefore, the problems of the treatment and disposal of radioactive wastes are important. The liquid and gaseous wastes with radioactivity concentrations below the maximum permissible levels are allowed to be disposed of on the sites by the law. However, high-level liquid wastes and solid wastes cannot be disposed of on the sites. These wastes stored in steel drums are collected by Japan Radioisotope Association, and finally treated and disposed of on the site of Japan Atomic Energy Research Institute. The nuclides used in hospitals are principally Tc-99m, and also 131 I, 198 Au, 125 I and 3 H. The following matters are described: the present situation, radioactive wastes from medical treatments, and the management of radioactive solid, liquid and gaseous wastes from hospitals. (J.P.N.)

Vertical oceanic transport of alpha-radioactive nuclides by zooplankton fecal pellets

International Nuclear Information System (INIS)

Higgo, J.J.W.; Cherry, R.D.; Heyraud, M.; Fowler, S.W.; Beasley, T.M.

1980-01-01

This paper gives the results of research to explain the role played by marine plankton metabolism in the vertical oceanic transport of the alpha-emitting nuclides. The common Mediterranean euphausiid, Meganyctiphanes norvegica, was selected as the typical zooplanktonic species that is the focus of this work. Measurements of 239 240 Pu, 238 U, 232 Th, and 210 Po are reported in whole euphausiids and in euphausiid fecal pellets and molts. The resulting data are inserted into a simple model that describes the flux of an element through a zooplanktonic animal. Concentrations of the nuclides concerned are high in fecal pellets, at levels which are typical of geological rather than biological material. It is suggested that zooplanktonic fecal pellets play a significant role in the vertical oceanic transport of plutonium, thorium, and polonium

The Performance Assessment of the Detector for the Portable Environmental Radiation Distribution Monitoring System with Rapid Nuclide Recognition

International Nuclear Information System (INIS)

Lee, Uk Jae; Kim, Hee Reyoung

2015-01-01

The environment radiation distribution monitoring system measures the radiation using a portable detector and display the overall radiation distribution. Bluetooth and RS-232 communications are used for constructing monitoring system. However RS-232 serial communication is known to be more stable than Bluetooth and also it can use the detector's raw data which will be used for getting the activity of each artificial nuclide. In the present study, the detection and communication performance of the developed detector with RS-232 method is assessed by using standard sources for the real application to the urban or rural environment. Assessment of the detector for the portable environmental radiation distribution monitoring system with rapid nuclide recognition was carried out. It was understood that the raw data of detector could be effectively treated by using RS-232 method and the measurement showed a good agreement with the calculation within the relative error of 0.4 % in maximum

The Performance Assessment of the Detector for the Portable Environmental Radiation Distribution Monitoring System with Rapid Nuclide Recognition

Energy Technology Data Exchange (ETDEWEB)

Lee, Uk Jae; Kim, Hee Reyoung [Ulsan National Institute of Science and Technology, Ulsan (Korea, Republic of)

2015-05-15

The environment radiation distribution monitoring system measures the radiation using a portable detector and display the overall radiation distribution. Bluetooth and RS-232 communications are used for constructing monitoring system. However RS-232 serial communication is known to be more stable than Bluetooth and also it can use the detector's raw data which will be used for getting the activity of each artificial nuclide. In the present study, the detection and communication performance of the developed detector with RS-232 method is assessed by using standard sources for the real application to the urban or rural environment. Assessment of the detector for the portable environmental radiation distribution monitoring system with rapid nuclide recognition was carried out. It was understood that the raw data of detector could be effectively treated by using RS-232 method and the measurement showed a good agreement with the calculation within the relative error of 0.4 % in maximum.

Interlaboratory comparison of environmental relevant nuclides with spinach powder as sample medium; Vergleichspruefung mit Spinatpulver als Probenart fuer umweltrelevante Nuklide

Energy Technology Data Exchange (ETDEWEB)

Roos, N.; Tait, D. [Max Rubner-Institut, Kiel (Germany). Leitstelle fuer Boden, Bewuchs, Futtermittel und Nahrungsmittel pflanzlicher und tierischer Herkunft

2014-01-20

Spinach is cited as a representative medium for leafy vegetables in the Integrated Measurement and Information System for the surveillance of environmental radioactivity (IMIS) in Germany. Fresh spinach, however, is not suitable in interlaboratory comparisons on the determination of spiked radionuclides because of the difficulties in homogeneously distributing the radionuclides and attaining a known specific activity in the samples. In contrast, spinach powder is finely milled, so that homogeneous distribution and known specific activities of the nuclides are more readily achievable. For this interlaboratory comparison spinach powder was mixed with the pure beta emitter Sr-90 and the gamma-emitting nuclides I-131, Cs-134 and Cs-137. After homogenization samples were dispatched to 77 laboratories from Germany and other European countries (59 in Germany, 5 in Switzerland, 4 each in the UK and Austria, and one each in France, Italy, the Netherlands, Ireland and Luxembourg). In addition to the added nuclides participants had to determine the natural radionuclide K-40. The participants were instructed to use a fast method for the determination of dry matter (DM). To check the homogeneity of the nuclide distribution 14 samples of the labeled spinach powder were randomly selected and analyzed in the Coordinating Laboratory for the Surveillance of Radioactivity in the Environment of the Max Rubner-Institute (MRI). According to DIN 13528:2005 the samples showed sufficient homogeneity of the added nuclides. For the evaluation of the interlaboratory comparison the Physikalisch-Technische Bundesanstalt (PTB) determined reference values for the the specific activities (Bq per kg DM) of the gamma emitters. The values with the expanded uncertainties (k = 2) were as follows: I-131: 181 ± 6 Bq/kg; Cs-134: 34.4 ± 1.1 Bq/kg; Cs-137: 11.1 ± 0.4 Bq/kg; K-40: 1240 ± 40 Bq/kg. Since a reference value of the PTB for the specific activity of Sr-90 was not available the general average

The Calculation Of Total Radioactivity Of Kartini Reactor Fuel Element

International Nuclear Information System (INIS)

Budisantoso, Edi Trijono; Sardjono, Y.

1996-01-01

The total radioactivity of Kartini reactor fuel element has been calculated by using ORIGEN2. In this case, the total radioactivity is the sum of alpha, beta, and gamma radioactivity from activation products nuclides, actinide nuclides and fission products nuclides in the fuel element. The calculation was based on irradiation history of fuel in the reactor core. The fuel element no 3203 has location history at D, E, and F core zone. The result is expressed in graphics form of total radioactivity and photon radiations as function of irradiation time and decay time. It can be concluded that the Kartini reactor fuel element in zone D, E, and F has total radioactivity range from 10 Curie to 3000 Curie. This range is for radioactivity after decaying for 84 days and that after reactor shut down. This radioactivity is happened in the fuel element for every reactor operation and decayed until the fuel burn up reach 39.31 MWh. The total radioactivity emitted photon at the power of 0.02 Watt until 10 Watt

Survey monitoring of environmental radioactivity in Chuncheon area

Energy Technology Data Exchange (ETDEWEB)

Cha, Moon Hoe.; Hwang, Sang Gyu [Chuncheon Regional Radioactivity Monitoring Station, Chuncheon (Korea, Republic of)

2002-12-15

Gross beta radioactivities in airborne dust, fallout, precipitation and tap water, and gamma exposure rates have been monitored periodically in 2002 at Chunchon Regional Radioactivity Monitoring Station. The concentrations of radioactive nuclide of {sup 7}Be and {sup 137}Cs on airborne dust, and {sup 7}Be, {sup 40}K and {sup 137}Cs on fallout, precipitation have been analyzed monthly. The {sup 7}Be, {sup 40}K, {sup 137}Cs etc. concentrations in the 19 foodstuffs(peanut, chestnut, walnut, pine nut acorn, oak mushroom, western mushroom, winter mushroom, oyster mushroom, coffee, green tea, ginseng tea, soils, cereals, vegetable, indicator plant) and 5 tap water sampled in Youngseo area of Kangwon-do have also been measured. No significant changes from the previous years have been found in gross beta radioactivities in environmental samples and gamma exposure rates. The concentrations of {sup 7}Be, {sup 40}K, and {sup 137}Cs nuclide in the foodstuffs sampled in Youngseo area are less(or slightly higher in some cases) than the MDA values, except {sup 40}K nuclide. All the concentrations of {sup 137}Cs nuclides in the water are less than the MDA values.

Survey monitoring of environmental radioactivity in Chuncheon area

Energy Technology Data Exchange (ETDEWEB)

Cha, Moon Hoe.; Hwang, Sang Gyu [Chuncheon Regional Radioactivity Monitoring Station, Chuncheon (Korea, Republic of)

2003-12-15

Gross beta radioactivities in airborne dust, fallout, precipitation and tap water, and gamma exposure rates have been monitored periodically in 2003 at Chunchon Regional Radioactivity Monitoring Station. The concentrations of radioactive nuclide of {sup 7}Be and {sup 137} Cs on airborne dust, and {sup 7}Be, {sup 40}K and {sup 137}Cs on fallout, precipitation have been analyzed monthly. The {sup 7}Be, {sup 40}K, {sup 137}Cs etc. concentrations in the 22 foodstuffs(peanut, chestnut, walnut, pine nut acorn, oak mushroom, western mushroom, winter mushroom, oyster mushroom, coffee, green tea, ginseng tea, soils, cereals, vegetable, indicator plant) and 10 tap water sampled in Youngseo area of Kangwon-do have also been measured. No significant changes from the previous years have been found in gross beta radioactivities in environmental samples and gamma exposure rates. The concentrations of {sup 7}Be, {sup 40}K, and {sup 137}Cs nuclide in the foodstuffs sampled in Youngseo area are less(or slightly higher in some cases) than the MDA values, except {sup 40}K nuclide. All the concentrations of {sup 137}Cs nuclides in the water are less than the MDA values.

Survey monitoring of environmental radioactivity in Chuncheon area

International Nuclear Information System (INIS)

Lee, Byung Ki.; Hwang, Sang Kyu

2001-12-01

Gross beta radioactivities in airborne dust, fallout, precipitation and tap water, and gamma exposure rates have been monitored periodically in 2001 at Chunchon Regional Radioactivity Monitoring Station. The concentrations of radioactive nuclide of 7 Be and 137 Cs on airborne dust, and 7 Be, 40 K and 137 Cs on fallout, precipitation have been analyzed monthly. The 7 Be, 40 K, 137 Cs and 226 Ra etc. concentrations in the 23 foodstuffs(potato, sweet potato, bean sprout, onion, pumpkin, spinach, welsh onion, radish leaves, red pepper, garlic, lettuce, apple, persimmon, orange, pear, grape, mackerel, Alaska pollack, hairtail, squid oyster, baby clam, mussel) and 5 tap water sampled in Youngseo area of Kangwon-do have also been measured. No significant changes from the previous years have been found in gross beta radioactivities in environmental samples and gamma exposure rates. The concentrations of 7 Be, 40 K, and 137 Cs nuclide in the foodstuffs sampled in Youngseo area are less(or slightly higher in some cases) than the MDA values, except 40 K nuclide. All the concentrations of 137 Cs and 226 Ra nuclides in the water are less than the MDA values

Technical support for GEIS: radioactive waste isolation in geologic formations. Volume 21. Ground water movement and nuclide transport

Energy Technology Data Exchange (ETDEWEB)

None

1978-04-01

This volume, TM-36/21 Ground Water Movement and Nuclide Transport, is one of a 23-volume series, ''Technical Support for GEIS: Radioactive Waste Isolation in Geologic Formations, Y/OWI/TM-36'' which supplements a ''Contribution to Draft Generic Environmental Impact Statement on Commercial Waste Management: Radioactive Waste Isolation in Geologic Formations, Y/OWI/TM-44.'' The series provides a more complete technical basis for the preconceptual designs, resource requirements, and environmental source terms associated with isolating commercial LWR wastes in underground repositories in salt, granite, shale and basalt. Wastes are considered from three fuel cycles: uranium and plutonium recycling of spent fuel and uranium-only recycling. The studies presented in this volume consider the effect of the construction of the repository and the consequent heat generation on the ground water movement. Additionally, the source concentrations and leach rates of selected radionuclides were studied in relation to the estimated ground water inflow rates. Studies were also performed to evaluate the long term migration of radionuclides as affected by the ground water flow. In all these studies, three geologic environments are considered; granite, shale and basalt.

Radioactivity handbook. Volume 2: radioactive disintegrations, radiations-matter interactions, applications of radioactivity

International Nuclear Information System (INIS)

Foos, J.; Bonfand, E.; Rimbert, J.N.

1994-01-01

This volume is the second one of a group of three. The first one exposed nuclides, with neutrons and protons in a stable building: atomic nucleus. Here is the second one with unstable, radioactive nucleus. After the description of different kinds of disintegrations, it is justified to follow radiations in matter and modifications attached to them; different uses of radioactivity are developed in medicine, age determination, industrial utilization and biology

News from the Library: The 8th edition Karlsruhe nuclide chart has been released

CERN Multimedia

CERN Library

2012-01-01

The 8th edition of the Karlsruhe Nuclide Chart contains new data not found in the 7th edition.   Since 1958, the well-known Karlsruhe Nuclide Chart has provided scientists with structured, valuable information on the half-lives, decay modes and energies of radioactive nuclides. The chart is used in many disciplines in physics (health physics, radiation protection, nuclear and radiochemistry, astrophysics, etc.) but also in the life and earth sciences (biology, medicine, agriculture, geology, etc.). The 8th edition of the Karlsruhe Nuclide Chart contains new data on 737 nuclides not found in the 7th edition. In total, nuclear data on 3847 experimentally observed ground states and isomers are presented. A new web-based version of this chart is in the final stages of development for use within the Nucleonica Nuclear Science Portal - a portal for which CERN has an institutional license. The chart is also available in paper format.   If you want to buy a paper version of the chart, ple...

An innovative method for determining the diffusion coefficient of product nuclide

Energy Technology Data Exchange (ETDEWEB)

Chen, Chih Lung [Dept. of Nuclear Back-end Management, Taiwan Power Company, Taipei (China); Wang, Tsing Hai [Dept. Biomedical Engineering and Environment Sciences, National Tsing Hua University, Hsinchu (China)

2017-08-15

Diffusion is a crucial mechanism that regulates the migration of radioactive nuclides. In this study, an innovative numerical method was developed to simultaneously calculate the diffusion coefficient of both parent and, afterward, series daughter nuclides in a sequentially reactive through-diffusion model. Two constructed scenarios, a serial reaction (RN{sub 1} → RN{sub 2} → RN{sub 3}) and a parallel reaction (RN{sub 1} → RN{sub 2}A + RN{sub 2}B), were proposed and calculated for verification. First, the accuracy of the proposed three-member reaction equations was validated using several default numerical experiments. Second, by applying the validated numerical experimental concentration variation data, the as-determined diffusion coefficient of the product nuclide was observed to be identical to the default data. The results demonstrate the validity of the proposed method. The significance of the proposed numerical method will be particularly powerful in determining the diffusion coefficients of systems with extremely thin specimens, long periods of diffusion time, and parent nuclides with fast decay constants.

Nuclide release from the near-field of a L/ILW repository

International Nuclear Information System (INIS)

Karlsson, L.G.; Hoeglund, L.O.; Pers, K.

1986-12-01

For Project Gewaehr 1985, the release of nuclides from a repository for low- and intermediate-level radioactive waste is calculated. The calculations are made for a reference design repository located in the marl host rock at the Oberbauen Stock reference site. The results are limited to the release of the nuclides from the waste through the engineered barriers into the surrounding host rock and will, therefore, constitute a source term for the far-field and biosphere calculations. The most probable nuclide transport mechanism is diffusion and releases are thus influenced by the nuclide diffusivities in the barriers, nuclide sorption and nuclide solubility limits. Degradation of the engineered concrete barriers is taken into account. The effects of convective flow through the barriers are described elsewhere. A near-field release model is presented. It consists of a set of computer programs suited to handel different repository designs, solubility limitations and the different waste categories. The release calculations were made for a base case in which best estimates of the parameters were used. Sensitivity to the choice of the most important parameters was tested by parameter variations. The numerical models used were checked by comparative calculations with different codes and similar data. The results of the base calculations show that near-field barriers will cause both a delay of the release to the far-field and a reduced rate of release. The sorbed nuclides, comprising the actinides and some activation and fission products, will be delayed by 10'000 years and have a maximum release rate of less than 10 -3 Ci/a each. The non-sorbed nuclides are delayed by only about 100 years and the maximum release rate is less than 10 -2 Ci per year and nuclide. The parameter variations and the design model tests gave only limited deviations from the base case results. (author)

Radioactive safety analysis and assessment of waste rock pile site in uranium tailings

International Nuclear Information System (INIS)

Liu Changrong; Liu Zehua; Wang Zhiyong; Zhou Xinghuo

2007-01-01

Based on theoretical calculation and in-situ test results, distribution and emissions of radioactive nuclides of uranium tailings impoundment and waste rock pile sites are analyzed in this paper. It is pointed out that 222 Rn is the main nuclide of uranium tailings impoundment and waste rock pile site. Also 222 Rn is the main source term of public dose. 222 Rn concentrations in the atmospheric environment around and individual dose to Rn gradually decrease with increasing distances to uranium tailings impoundment and waste rock pile site. Based on in-situ tests on five uranium tailings impoundment and waste rock pile sites, a decisive method and safety protection distance are presented, which can be used to guide the validation and design of radioactive safety protection in uranium tailings impoundment and waste rock pile sites. (authors)

Method Development for Rapid Analysis of Natural Radioactive Nuclides Using Sector Field Inductively Coupled Plasma Mass Spectrometry

Energy Technology Data Exchange (ETDEWEB)

Lim, J.M.; Ji, Y.Y.; Lee, H.; Park, J.H.; Jang, M.; Chung, K.H.; Kang, M.J.; Choi, G.S. [Korea Atomic Energy Research Institute (Korea, Republic of)

2014-07-01

As an attempt to reduce the social costs and apprehension arising from radioactivity in the environment, an accurate and rapid assessment of radioactivity is highly desirable. Naturally occurring radioactive materials (NORM) are widely spread throughout the environment. The concern with radioactivity from these materials has therefore been growing for the last decade. In particular, radiation exposure in the industry when handling raw materials (e.g., coal mining and combustion, oil and gas production, metal mining and smelting, mineral sands (REE, Ti, Zr), fertilizer (phosphate), and building materials) has been brought to the public's attention. To decide the proper handling options, a rapid and accurate analytical method that can be used to evaluate the radioactivity of radionuclides (e.g., {sup 238}U, {sup 235}U, {sup 232}Th, {sup 226}Ra, and {sup 40}K) should be developed and validated. Direct measuring methods such as alpha spectrometry, a liquid scintillation counter (LSC), and mass-spectrometry are usually used for the measurement of radioactivity in NORM samples, and they encounter the most significant difficulties during pretreatment (e.g., purification, speciation, and dilution/enrichment). Since the pretreatment process consequently plays an important role in the measurement uncertainty, method development and validation should be performed. Furthermore, a-spectrometry has a major disadvantage of a long counting time, while it has a prominent measurement capability at a very low activity level of {sup 238}U, {sup 235}U, {sup 232}Th, and {sup 226}Ra. Contrary to the α-spectrometry method, a measurement technique using ICP-MS allow radioactivity in many samples to be measured in a short time period with a high degree of accuracy and precision. In this study, a method was developed for a rapid analysis of natural radioactive nuclides using ICP-MS. A sample digestion process was established using LiBO{sub 2} fusion and Fe co-precipitation. A magnetic

Determination of the Concentration of Radioactive Nuclides of Surface Soils of some Hadhramout's Valleys in Yemen Using Gamma-Ray Spectrometry

International Nuclear Information System (INIS)

Bazohair, A. O.; Bayashoot, A. K.; AL-Shamy, A. A.

2004-01-01

In this research five surface soil samples have been taken from some Hadhramout's valleys in Yemen (Khrid , Arf , Huwayrah , Buwaish, Khirba ) in the years from (1999) to (2002) and analyzed using gamma-ray spectrometry. The spectra of samples were measured using multichannel analyzer (MCA) that was connected with measurement system for this purpose.A high purity germanium(Hp Ge) detector with resolution of (2.11 keV) at gamma-line(1332 keV) of radioactive source(Co-60) used for detecting ( U 238 , Th 232 , K 40 , Cs 137 ) in the samples. The results showed that the average concentration of radioactive nuclides in the samples of uranium ranged from(37.56 Bq/Kg) to(46.58 Bq/Kg) and for thorium ranged from(37.93 Bq/Kg) to(47.28 Bq/Kg) and for potassium ranged from(347.57 Bq/Kg) to(850.10 Bq/Kg) and for cesium ranged from(6.94 Bq/Kg) to(15.86 Bq/Kg) and the measured precision of samples ranged from(4.71%) to (9.23%). (authors)

Survey monitoring of environmental radioactivity in Chuncheon area

Energy Technology Data Exchange (ETDEWEB)

Lee, Byung Ki.; Hwang, Sang Kyu [Chuncheon Regional Radioactivity Monitoring Station, Chuncheon (Korea, Republic of)

2001-12-15

Gross beta radioactivities in airborne dust, fallout, precipitation and tap water, and gamma exposure rates have been monitored periodically in 2001 at Chunchon Regional Radioactivity Monitoring Station. The concentrations of radioactive nuclide of {sup 7}Be and {sup 137}Cs on airborne dust, and {sup 7}Be, {sup 40}K and {sup 137}Cs on fallout, precipitation have been analyzed monthly. The {sup 7}Be, {sup 40}K, {sup 137}Cs and {sup 226}Ra etc. concentrations in the 23 foodstuffs(potato, sweet potato, bean sprout, onion, pumpkin, spinach, welsh onion, radish leaves, red pepper, garlic, lettuce, apple, persimmon, orange, pear, grape, mackerel, Alaska pollack, hairtail, squid oyster, baby clam, mussel) and 5 tap water sampled in Youngseo area of Kangwon-do have also been measured. No significant changes from the previous years have been found in gross beta radioactivities in environmental samples and gamma exposure rates. The concentrations of {sup 7}Be, {sup 40}K, and {sup 137}Cs nuclide in the foodstuffs sampled in Youngseo area are less(or slightly higher in some cases) than the MDA values, except {sup 40}K nuclide. All the concentrations of {sup 137}Cs and {sup 226}Ra nuclides in the water are less than the MDA values.

Survey monitoring of environmental radioactivity in Chuncheon area

Energy Technology Data Exchange (ETDEWEB)

Lee, Byung Ki.; Hwang, Sang Kyu [Chuncheon Regional Radioactivity Monitoring Station, Chuncheon (Korea, Republic of)

2000-12-15

Gross beta radioactivities in airborne dust, fallout, precipitation and tap water, and gamma exposure rates have been monitored periodically in 2000 at Chunchon Regional Radioactivity Monitoring Station. The concentrations of radioactive nuclide of {sup 7}Be and {sup 137}Cs on airborne dust, and {sup 7}Be, {sup 40}K and {sup 137}Cs on fallout, precipitation have been analyzed monthly. The {sup 7}Be, {sup 40}K, {sup 137}Cs and {sup 226}Ra etc. concentrations in the 23 foodstuffs(potato, sweet potato, bean sprout, onion, pumpkin, spinach, welsh onion, radish leaves, red pepper, garlic, lettuce, apple, persimmon, orange, pear, grape, mackerel, Alaska pollack, hairtail, squid oyster, baby clam, mussed) and 5 tap water sampled in Youngsoe area of Kangwon-do have also been measured. No significant changes from the previous years have been found in gross beta radioactivities in environmental samples and gamma exposure rates. The concentrations of {sup 7}Be, {sup 40}K, and {sup 137}Cs nuclide in the foodstuffs sampled in Youngseo area are less(or slightly higher in some cases) than the MDA value, except {sup 40}K nuclide. The concentrations of {sup 137}Cs and {sup 226}Ra nuclide in tap water are less(or is slightly higher in one sample) than the MDA value.

Analytical approach to the evaluation of nuclide transmutations

International Nuclear Information System (INIS)

Vukadin, Z.; Osmokrovic, P.

1995-01-01

Analytical approach to the evaluation of nuclide concentrations in a transmutation chain is presented. Non singular Bateman coefficients and depletion functions are used to overcome numerical difficulties when applying well-known Bateman solution of a simple radioactive decay. Method enables evaluation of complete decay chains without elimination of short lived radionuclides. It is efficient and accurate. Practical application of the method is demonstrated by computing the neptunium series inventory in used Candu TM fuel. (author)

Square chart of nuclides with the best coordinates

International Nuclear Information System (INIS)

Wang Yuying

2001-01-01

It analyzes upper limiting feature of even Z=60-82 in different charts of nuclides. It has illustrated that the break line of upper limiting Z=60-82 in the chart of nucleus with proton number Z and neutron number N, parameters Z and H (=N-Z), two new parameters S(=2Z-N) and H, and parameters K (=S-H) and H, in proper order, it shows that the break line trends from the left lower to the right upper, the line alternates with horizontal and vertical, and the line trends from the right lower to the left upper. Here it finds that the square chart of nuclides places the middle among these charts. It shows that nuclei distribution is concentrated, so are scope of whole region of nuclides in the different charts of nuclides

Measurement of soluble nuclide dissolution rates from spent fuel

International Nuclear Information System (INIS)

Wilson, C.N.; Gray, W.J.

1990-01-01

Gaining a better understanding of the potential release behavior of water-soluble radionuclides is the focus of new laboratory spent fuel dissolution studies being planned in support of the Yucca Mountain Project. Previous studies have suggested that maximum release rates for actinide nuclides, which account for most of the long-term radioactivity in spent fuel, should be solubility-limited and should not depend on the characteristics or durability of the spent fuel waste form. Maximum actinide concentrations should be sufficiently low to meet the NRC (Nuclear Regulatory Commission) annual release limits. Potential release rates for soluble nuclides such as 99 Tc, 135 Cs, 14 C and 129 I, which account for about 1-2% of the activity in spent fuel at 1,000 years, are less certain and may depend on processes such as oxidation of the fuel in the repository air environment. Dissolution rates for several soluble nuclides have been measured from spent fuel specimens using static and semi-static methods. However, such tests do not provide a direct measurement of fuel matrix dissolution rates that may ultimately control soluble-nuclide release rates. Flow-through tests are being developed as a potential supplemental method for determining the matrix component of soluble-nuclide dissolution. Advantages and disadvantages of both semi-static and flow-through methods are discussed. Tests with fuel specimens representing a range of potential fuel states that may occur in the repository, including oxidized fuel, are proposed. Preliminary results from flow-through tests with unirradiated UO 2 suggesting that matrix dissolution rates are very sensitive to water composition are also presented

Development of a Radioactive Waste Assay System

Energy Technology Data Exchange (ETDEWEB)

Kang, Duck Won; Song, Myung Jae; Shin, Sang Woon; Sung, Kee Bang; Ko, Dae Hach [Korea Electric Power Research Institute, Taejon (Korea, Republic of); Kim, Kil Jeong; Park, Jong Mook; Jee, Kwang Yoong [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

1996-12-31

Nuclear Act of Korea requires the manifest of low and intermediate level radioactive waste generated at nuclear power plants prior to disposal sites.Individual history records of the radioactive waste should be contained the information about the activity of nuclides in the drum, total activity, weight, the type of waste. A fully automated nuclide analysis assay system, non-destructive analysis and evaluation system of the radioactive waste, was developed through this research project. For the nuclides that could not be analysis directly by MCA, the activities of the representative {gamma}-emitters(Cs-137, Co-60) contained in the drum were measured by using that system. Then scaling factors were used to calculate the activities of {alpha}, {beta}-emitters. Furthermore, this system can automatically mark the analysis results onto the drum surface. An automated drum handling system developed through this research project can reduce the radiation exposure to workers. (author). 41 refs., figs.

Modeling study on nuclide transport in ocean - an ocean compartment method

International Nuclear Information System (INIS)

Lee, Youn Myoung; Suh, Kyung Suk; Han, Kyoung Won

1991-01-01

An ocean compartment model simulating transport of nuclides by advection due to ocean circulation and interaction with suspended sediments is developed, by which concentration breakthrough curves of nuclides can be calculated as a function of time. Dividing ocean into arbitrary number of characteristic compartments and performing a balance of mass of nuclides in each ocean compartment, the governing equation for the concentration in the ocean is obtained and a solution by the numerical integration is obtained. The integration method is specially useful for general stiff systems. For transfer coefficients describing advective transport between adjacent compartments by ocean circulation, the ocean turnover time is calculated by a two-dimensional numerical ocean method. To exemplify the compartment model, a reference case calculation for breakthrough curves of three nuclides in low-level radioactive wastes, Tc-99, Cs-137, and Pu-238 released from hypothetical repository under the seabed is carried out with five ocean compartments. Sensitivity analysis studies for some parameters to the concentration breakthrough curves are also made, which indicates that parameters such as ocean turnover time and ocean water volume of compartments have an important effect on the breakthrough curves. (Author)

Evaluation of Nuclide Release Scenarios for a Hypothetical LILW Repository

International Nuclear Information System (INIS)

Lee, Youn Myoung; Jeong, Jong Tae

2010-11-01

A program for the safety assessment and performance evaluation of a low- and intermediate-level radioactive waste (LILW) repository system has been developed. Utilizing GoldSim (GoldSim, 2006), the program evaluates nuclide release and transport into the geosphere and biosphere under various disruptive natural and manmade events and scenarios that can occur after a waste package failure. We envisaged and illustrated these events and scenarios as occurring after the closure of a hypothetical LILW repository, and they included the degradation of various manmade barriers, pumping well drilling, and natural disruptions such as the sudden formation of a preferential flow pathway in the far-field area of the repository. Possible enhancement of nuclide transport facilitated by colloids or chelating agents is also dealt with. We used the newly-developed GoldSim template program, which is capable of various nuclide release scenarios and is greatly suited for simulating a potential repository given the geological circumstances in Korea, to create the detailed source term and near-field release scheme, various nuclide transport modes in the far-field geosphere area, and the biosphere transfer. Even though all parameter values applied to the hypothetical repository were assumed, the illustrative results, particularly the probabilistic calculations and sensitivity studies, may be informative under various scenarios

Refilling material for underground disposal of radioactive waste

International Nuclear Information System (INIS)

Yajima, Tatsuya; Kato, Hiroyasu.

1995-01-01

Generally, the underground circumstance where radioactive wastes are to be processed is in high pH and highly ionized state due to ingredients leached out of cement of a concrete pit and solidifying products. A refilling material for underground disposal are demanded to adsorb radioactive nuclides such as 137 Cs even in such a state. As the refilling material, a mixture of bentonite and sintered vermiculite, preferably, comprising 10 to 40wt% of vermiculite is used. The refilling material has a high water hold out barrier performance of bentonite and a high radioactive nuclide adsorbing performance of vermiculite. In a state of highly ionized state when the adsorbing performance of bentonite is reduced, the nuclide-absorbing performance is improved by vermiculite and since the content of the vermiculite is not more than 40wt%, the water hold out barrier performance of the bentonite is not deteriorated. (N.H.)

[The fate of nuclides in natural water systems

International Nuclear Information System (INIS)

Turekian, K.K.

1989-01-01

Our research at Yale on the fate of nuclides in natural water systems has three components to it: the study of the atmospheric precipitation of radionuclides and other chemical species; the study of the behavior of natural radionuclides in groundwater and hydrothermal systems; and understanding the controls on the distribution of radionuclides and stable nuclides in the marine realm. In this section a review of our progress in each of these areas is presented

Nuclide radioactive decay data uncertainties library

International Nuclear Information System (INIS)

Barabanova, D S; Zherdev, G M

2017-01-01

The results of the developing the library of uncertainties of radioactive decay data in the ABBN data library format are described. Different evaluations of uncertainties were compared and their effects on the results of calculations of residual energy release were determined using the test problems and experiment. Tables were generated in the ABBN format with the data obtained on the basis of libraries in ENDF-6 format. 3821 isotopes from the ENDF/B-7 data library, 3852 isotopes from the JEFF-3.11 data library and 1264 isotopes from the JENDL-4.0 data library were processed. It was revealed that the differences in the evaluations accepted in different decay data libraries are not so big, although they sometimes exceed the uncertainties assigned to the data in the ENDF/B-7 and JEFF-3.11 libraries, which as a rule, they agree with each other. On the basis of developed method it is supposed to create a library of data uncertainties for radioactive decay within the constant data system in FSUE RFNC-VNIIEF with its further connection with CRYSTAL module. (paper)

Analysis of radioactive cobalt

International Nuclear Information System (INIS)

1977-01-01

This is a manual published by Science and Technology Agency, Japan, which prescribes on the analysis method for radioactive cobalt which is a typical indexing nuclide among the radioactive nuclides released from nuclear facilities. Since the released cobalt is mainly discharged to coastal region together with waste water, this manual is written for samples of sea water, sea bottom sediments and marine organisms. Radioactive cobalt includes the nuclides of 57 co, 58 Co, 60 Co, etc., the manual deals with them as a whole as 60 Co of long half life. Though 60 Co analysis has become feasible comparatively simply due to scintillation or semi-conductor spectrometry, trace 60 Co analysis is performed quantitatively by co-precipitation or collection into alumina and scintillation spectrometry. However, specific collecting operation and γ-γ coincidence measurement have been required so far. This manual employs 60 Co collection by means of ion-exchange method and measurement with low background GM counting system, to analyze quantitatively and rapidly low level 60 Co. It is primarily established as the standard analyzing method for the survey by local autonomous bodies. It is divided into 4 chapters including introduction sea water, marine organisms, and sea bottom sediments. List of required reagents is added in appendix. (Wakatsuki, Y.)

A Probabilistic Consideration on Nuclide Releases from a Pyro-processed Waste Repository

Energy Technology Data Exchange (ETDEWEB)

Lee, Youn Myoung; Jeong, Jong Tae [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2012-05-15

Very recently, a GoldSim template program, GSTSPA, for a safety assessment of a conceptual hybrid-typed repository system, called 'A-KRS,' in which two kinds of pyroprocessed radioactive wastes, low-level metal wastes and ceramic high-level wastes that arise from the pyroprocessing of PWR nuclear spent fuels, has been developed and is to be disposed of by 'separate disposal' strategies. The A-KRS is considered to be constructed at two different depths in geological media: at a 200m depth, at which a possible human intrusion is considered to be limited after closure, for the pyroprocessed metal wastes with lower or no decay heat producing nuclides, and at a 500m depth, believed to be the reducing condition for nuclides with a rather higher radioactivity and heat generation rate. This program is ready for a probabilistic total system performance assessment (TSPA) which is able to evaluate nuclide release from the repository and farther transport into the geosphere and biosphere under various normal, disruptive natural and manmade events, and scenarios that can occur after a failure of a waste package and canister with associated uncertainty. To quantify the nuclide release and transport through the various possible pathways in the near- and far-fields of the A-KRS repository system under a normal groundwater flow scenario, some illustrative evaluations have been made through this study. Even though all parameter values associated with the A-KRS were assumed for the time being, the illustrative results should be informative since the evaluation of such releases is very important not only in view of the safety assessment of the repository, but also for design feedback of its performance

A Probabilistic Consideration on Nuclide Releases from a Pyro-processed Waste Repository

International Nuclear Information System (INIS)

Lee, Youn Myoung; Jeong, Jong Tae

2012-01-01

Very recently, a GoldSim template program, GSTSPA, for a safety assessment of a conceptual hybrid-typed repository system, called 'A-KRS,' in which two kinds of pyroprocessed radioactive wastes, low-level metal wastes and ceramic high-level wastes that arise from the pyroprocessing of PWR nuclear spent fuels, has been developed and is to be disposed of by 'separate disposal' strategies. The A-KRS is considered to be constructed at two different depths in geological media: at a 200m depth, at which a possible human intrusion is considered to be limited after closure, for the pyroprocessed metal wastes with lower or no decay heat producing nuclides, and at a 500m depth, believed to be the reducing condition for nuclides with a rather higher radioactivity and heat generation rate. This program is ready for a probabilistic total system performance assessment (TSPA) which is able to evaluate nuclide release from the repository and farther transport into the geosphere and biosphere under various normal, disruptive natural and manmade events, and scenarios that can occur after a failure of a waste package and canister with associated uncertainty. To quantify the nuclide release and transport through the various possible pathways in the near- and far-fields of the A-KRS repository system under a normal groundwater flow scenario, some illustrative evaluations have been made through this study. Even though all parameter values associated with the A-KRS were assumed for the time being, the illustrative results should be informative since the evaluation of such releases is very important not only in view of the safety assessment of the repository, but also for design feedback of its performance

Calculation of total number of disintegrations after intake of radioactive nuclides using the pseudo inverse matrix

International Nuclear Information System (INIS)

Noh, Si Wan; Sol, Jeong; Lee, Jai Ki; Lee, Jong Il; Kim, Jang Lyul

2012-01-01

Calculation of total number of disintegrations after intake of radioactive nuclides is indispensable to calculate a dose coefficient which means committed effective dose per unit activity (Sv/Bq). In order to calculate the total number of disintegrations analytically, Birch all's algorithm has been commonly used. As described below, an inverse matrix should be calculated in the algorithm. As biokinetic models have been complicated, however, the inverse matrix does not exist sometime and the total number of disintegrations cannot be calculated. Thus, a numerical method has been applied to DCAL code used to calculate dose coefficients in ICRP publication and IMBA code. In this study, however, we applied the pseudo inverse matrix to solve the problem that the inverse matrix does not exist for. In order to validate our method, the method was applied to two examples and the results were compared to the tabulated data in ICRP publication. MATLAB 2012a was used to calculate the total number of disintegrations and exp m and p inv MATLAB built in functions were employed

Regulations on radioactive waste in hospitals

International Nuclear Information System (INIS)

Beiso, M.L.

2017-01-01

In hospitals that have a radiotherapy service, the contaminated sewage follows a specific way, first it comes from specific toilets that must be use by patients undergoing a radiotherapy treatment, and secondly it is stored in tanks and its radioactivity is measured regularly and when the radioactivity level is in conformity with regulations, sewage is disposed as any non-contaminated sewage. Regulations impose a radioactive level below 100 Becquerel per liter for I 131 and 10 Becquerel per liter for other nuclides for the sewage to be disposed. A new system named ST-10 allows the in-line and real-time measurement and the identification of nuclides in sewage and can say if the measured values are consistent with the patient treatment. (A.C.)

Multi-pathway model of nuclide transport in fractured media and its application

International Nuclear Information System (INIS)

Li Xun; Yang Zeping; Li Jinxuan

2010-01-01

In order to know the law of nuclide transport in fracture system, the basic differential equations of nuclide transport in fracture and matrix were obtained based on the dual media theory, and the general analytic solutions of nuclide transport in single fractured media with exponential attenuation source in fracture were deduced by Laplace transform, and one-dimensional multi-pathway model of nuclide transport was proposed based on dual media theory and stochastic distribution of fracture parameters. The transport of Th-229, Cs-135 and Se-79 were simulated with this model, the relative concentration of these nuclides in fracture system were predicted. Further more, it was deduced that aperture and velocity can distinctly influence transport of nuclide by comparing with the results which were simulated by single fracture model. (authors)

Treatment of short-lived radioactive wastes

International Nuclear Information System (INIS)

Yamaguchi, Chiri

1976-01-01

Recently short life nuclides have come to be utilized increasingly as diagnostic radioisotopes, and Tc-99m (half-life; 6.05 hours) and Ga-67 (half-life 7.79 hours) are replacing the most nuclides fomerly used in vivo test. Such development of radioactive products inevitably causes the rapid increase of their wastes. At present, the radioactive wastes produced by hospitals and university laboratories in Japan are collected by the Japan Radioisotope Association, and treated by the Japan Atomic Energy Research Institute. These wastes are divided into combustibles and incombustibles to store in the store house in the Japan Atomic Energy Research Institute. The present law in Japan contains the contradiction which treats the matter with one several millionth of radioactivity after decay same as the original radioactive matter. Thus solid must be stored permanently, while gas and liquid can be discharged after dilution. (Kobatake, H.)

Radioactivity Distribution in Malaysian Marine Environment. Chapter 4

International Nuclear Information System (INIS)

Zal U'yun Wan Mahmood; Abdul Kadir Ishak; Norfaizal Mohamad; Wo, Y.M.; Kamarudin Samuding

2015-01-01

The marine radioactivity distribution mapping in malaysia was developed with the aim to illustrate the pattern of the distribution of both anthropogenic and natural radionuclides in seawater and sediments. The data collected will form the basis for an anthropogenic radioactivity.

Selection of exception limits for all actinide nuclides based on revised criteria for safe international transport

International Nuclear Information System (INIS)

Lavarenne, C.; Rouyer, V.; Sert, G.; Mennerdahl, D.; Dean, C.; Barton, N.; Jean, F.

2003-01-01

Since 1998, there have been some speculations about future transport of significant quantities and concentrations of other actinide nuclides than the four currently listed in the regulation for the safe transport of the radioactive material. Therefore, it raised a need to specify exception limits for such actinides. Additionally, the total fissile nuclide mass per consignment of excepted packages was limited in the 1996 edition of the regulations (a conveyance limit is preliminary supported in the 2003 revision). The proposed changes of the rules have to take this new control into account. The European Community (DGTREN) decided to fund a project related to this subject. In order to define credible exception limits, it was necessary to have reasonably accurate data for all actinide nuclides. Then the authors of the study decided to perform calculations with different codes (MONK, MCNP, CRISTAL, SCALE) and different cross-section libraries (JEF2.2, ENDFB, JENDL, etc.). This article presents the work achieved and gives propositions of modification for the IAEA requirements for the Safe Transport of Radioactive Material related to, firstly, the list of the fissile materials, and secondly, the rule to determine the quantities of actinide nuclides that can be excepted from the requirements for the packages containing fissile materials. The participants acknowledge the DGTREN who made this work possible due to its support. (author)

Spreadsheet application to classify radioactive material for shipment

International Nuclear Information System (INIS)

Brown, A.N.

1997-12-01

A spreadsheet application has been developed at the Idaho National Engineering and Environmental Laboratory to aid the shipper when classifying nuclide mixtures of normal form, radioactive materials. The results generated by this spreadsheet are used to confirm the proper US Department of Transportation (DOT) classification when offering radioactive material packages for transport. The user must input to the spreadsheet the mass of the material being classified, the physical form (liquid or not), and the activity of each regulated nuclide. The spreadsheet uses these inputs to calculate two general values: (1) the specific activity of the material, and (2) a summation calculation of the nuclide content. The specific activity is used to determine if the material exceeds the DOT minimal threshold for a radioactive material (Yes or No). If the material is calculated to be radioactive, the specific activity is also used to determine if the material meets the activity requirement for one of the three Low Specific Activity designations (LSA-I, LSA-II, LSA-III, or Not LSA). Again, if the material is calculated to be radioactive, the summation calculation is then used to determine which activity category the material will meet (Limited Quantity, Type A, Type B, or Highway Route Controlled Quantity)

Study of relationship between radioactivity distribution, contamination burden and quality standard, accommodate energy of code river Yogyakarta

International Nuclear Information System (INIS)

Agus Taftazani and Muzakky

2009-01-01

Study of relationship between distribution, contamination burden of gross β radioactivity and natural radionuclide in water and sediment sample from 11 observation station Code river to quality standard and maximum capacity of Code river have been done. Natural radio nuclides identification and gross β radioactivity measurement of condensed water, dry and homogeneous sediment powder (past through 100 mesh sieve) samples have been done by using spectrometer and GM counter. Radioactivity data was analyzed descriptive with histogram to show the spreading pattern of data. Contamination burden data, quality standard and maximum capacity of river Code was to descriptive analyzed by line diagram to knowing relationship between contamination burden, quality standard, and maximum capacity of Code river. The observation of water and sediment at 11 observation station show that the emitter natural radionuclides: 210 Pb, 212 Pb, 214 Pb, 226 Ra, 208 Tl, 214 Bi, 228 Ac and 40 K were detected. The analytical result conclusion was that the pattern spread of average activity gross β and were increase from upstream to downstream of the Code river samples. Contamination burden, quality standard and maximum capacity of radionuclide activity of 210 Pb, 212 Pb, 226 Ra and 228 Ac were more smaller than quality standard of river water according to regulation of Nuclear Energy Regulatory Agency 02/Ka-BAPETEN/V-99 concerning quality standard of radioactivity. It’s mean that Code river still in good contamination burden for the four radionuclides. (author)

Measurement of gross beta radioactivity in high-level liquid waste

International Nuclear Information System (INIS)

Lu Feng; Lin Cansheng; Zhang Xianzi; Chen Guoan; Zhang Chonghai

1992-01-01

Using beta plastic scintillation counter of low level background, gross beta radioactivity of twelve samples for high-level liquid waste is determined directly. Beta efficiency curves of plastic scintillation counter for four mass thickness are calibrated in advance. Determining gross beta radioactivity, gross efficiency of the scintillation counter for various energy beta ray is calculated via weighted mean method with the ratio of radioactivity for each nuclide. The ratio of radioactivity for nuclides which have gamma disintegration is determined in terms of the radioactivity measured by gamma spectrometer. The ratio of the radioactivity for 90 Sr which has purity beta disintegration is calculated in terms of half life time approximation. The ratio of the radioactivity for 147 Pm which also has purity disintegration is calculated by means of apparent cooling-time approximation. The uncertainty of results for the present work is about +-15%

An experiment on radioactive equilibrium and its modelling using the ‘radioactive dice’ approach

Science.gov (United States)

Santostasi, Davide; Malgieri, Massimiliano; Montagna, Paolo; Vitulo, Paolo

2017-07-01

In this article we describe an educational activity on radioactive equilibrium we performed with secondary school students (17-18 years old) in the context of a vocational guidance stage for talented students at the Department of Physics of the University of Pavia. Radioactive equilibrium is investigated experimentally by having students measure the activity of 214Bi from two different samples, obtained using different preparation procedures from an uraniferous rock. Students are guided in understanding the mathematical structure of radioactive equilibrium through a modelling activity in two parts. Before the lab measurements, a dice game, which extends the traditional ‘radioactive dice’ activity to the case of a chain of two decaying nuclides, is performed by students divided into small groups. At the end of the laboratory work, students design and run a simple spreadsheet simulation modelling the same basic radioactive chain with user defined decay constants. By setting the constants to realistic values corresponding to nuclides of the uranium decay chain, students can deepen their understanding of the meaning of the experimental data, and also explore the difference between cases of non-equilibrium, transient and secular equilibrium.

Selection of exception limits for all actinide nuclides based on revised criteria for safe international transport and including storage delay

International Nuclear Information System (INIS)

Lavarenne, C.; Rouyer, V.; Mennerdahl, D.; Dean, C.; Barton, N.; Jean, F.

2004-01-01

Since 1998, there have been some speculations about future transport of significant quantities and concentrations of other actinide nuclides than the four currently listed in the regulation for the safe transport of the radioactive material. Therefore, it raised a need to specify exception limits for such actinides. In order to define credible exception limits, it was necessary to have reasonably accurate data for all actinide nuclides. Then the DGTREN/participants decided to perform calculations with different codes (MONK, MCNP, CRISTAL and SCALE) and different cross-section libraries (JEF2.2, ENDFB, etc.). The parameters of interest (such as k-infinite, critical masses) were determined. This article presents the work achieved and the questions raised, e.g. related to the effect of the radioactive decay of the isotopes on the criticality risks. It also points out the need for an evolution of the regulation of the safe transport of radioactive materials and gives a proposition of modification for the IAEA requirements related to, firstly, the list of the fissile materials, secondly, the rule to determine the quantities of actinide nuclides that can be excepted from the requirements for the packages containing fissile materials

Bioremediation system on-line for removal radionuclides in radioactive waters

International Nuclear Information System (INIS)

Belinchon, J. A.; Garcia, A. M.; Ruibal, C.; Moreno, D. A.

2010-01-01

In previous studies developed in Cofrentes Nuclear Power Plant (Valencia, Spain), has been observed that the microorganisms in the radioactive waters of the spent nuclear fuel pool are capable of colonizing the metallic surfaces of the walls and pipes and perform biofilm. These biofilm retain the nuclides contributing to decontaminate the water. In this project, carried out in Cofrentes Nuclear Power Plant, a pilot plant has been designed for the bio decontamination of the radioactive water. At present, the radioactive water coming from the spent nuclear fuel pools, pass through ionic exchange resins. After, these resins are managed as radioactive waste. In this project, the water passes through a bioreactor with stainless steel balls capable of being colonized by the microorganisms in the water. Inside the bioreactor the water gets in contact with the material of the balls, and a biofilm, which retains the nuclides in the water, is developed. The biofilm is easily removed by any conventional procedure of radiochemical decontamination of materials and the nuclides can be collected in a small volume for recovery final disposition or containment. Later, the material of the bioreactor could be managed as not radioactive material. (Author) 9 refs.

Migration studies of fission product nuclides in rocks. Pt.5: Diffusion and permeability of nuclide 125I in marble

International Nuclear Information System (INIS)

Wen Ruiyuan; Gao Hongcheng; Wang Xiangyun

1996-01-01

The migration behaviour of nuclide 125 I, as a simulation of the long lived fission product 129 I, in marble is studied in self-designed cells. A series of the most important parameters of diffusion and permeability (e.g., intrinsic diffusion coefficient, dispersion coefficient and interstitial flow velocity, etc.) are determined. Based on the differential equation of the nuclide migration, the distribution function and numerical solution of 125 I in marble are presented. The results show that the migration velocity of 125 I in marble is fast, indicating that it is not suitable to dispose nuclear waste in marble

Calculated nuclide production yields in relativistic collisions of fissile nuclei

Energy Technology Data Exchange (ETDEWEB)

Benlliure, J.; Schmidt, K.H. [Gesellschaft fuer Schwerionenforschung mbH, Darmstadt (Germany); Grewe, A.; Jong, M. de [Technische Univ. Darmstadt (Germany). Inst. fuer Kernphysik; Zhdanov, S. [AN Kazakhskoj SSR, Alma-Ata (USSR). Inst. Yadernoj Fiziki

1997-11-01

A model calculation is presented which predicts the complex nuclide distribution resulting from peripheral relativistic heavy-ion collisions involving fissile nuclei. The model is based on a modern version of the abrasion-ablation model which describes the formation of excited prefragments due to the nuclear collisions and their consecutive decay. The competition between the evaporation of different light particles and fission is computed with an evaporation code which takes dissipative effects and the emission of intermediate-mass fragments into account. The nuclide distribution resulting from fission processes is treated by a semiempirical description which includes the excitation-energy dependent influence of nuclear shell effects and pairing correlations. The calculations of collisions between {sup 238}U and different reaction partners reveal that a huge number of isotopes of all elements up to uranium is produced. The complex nuclide distribution shows the characteristics of fragmentation, mass-asymmetric low-energy fission and mass-symmetric high-energy fission. The yields of the different components for different reaction partners are studied. Consequences for technical applications are discussed. (orig.)

Radioactivity in food crops

International Nuclear Information System (INIS)

Drury, J.S.; Baldauf, M.F.; Daniel, E.W.; Fore, C.S.; Uziel, M.S.

1983-05-01

Published levels of radioactivity in food crops from 21 countries and 4 island chains of Oceania are listed. The tabulation includes more than 3000 examples of 100 different crops. Data are arranged alphabetically by food crop and geographical origin. The sampling date, nuclide measured, mean radioactivity, range of radioactivities, sample basis, number of samples analyzed, and bibliographic citation are given for each entry, when available. Analyses were reported most frequently for 137 Cs, 40 K, 90 Sr, 226 Ra, 228 Ra, plutonium, uranium, total alpha, and total beta, but a few authors also reported data for 241 Am, 7 Be, 60 Co, 55 Fe, 3 H, 131 I, 54 Mn, 95 Nb, 210 Pb, 210 Po, 106 Ru, 125 Sb, 228 Th, 232 Th, and 95 Zr. Based on the reported data it appears that radioactivity from alpha emitters in food crops is usually low, on the order of 0.1 Bq.g -1 (wet weight) or less. Reported values of beta radiation in a given crop generally appear to be several orders of magnitude greater than those of alpha emitters. The most striking aspect of the data is the great range of radioactivity reported for a given nuclide in similar food crops with different geographical origins

Cosmic disposal of radioactive waste

Energy Technology Data Exchange (ETDEWEB)

Inoue, Y; Morisawa, S [Kyoto Univ. (Japan). Faculty of Engineering

1975-03-01

The technical and economical possibility and safety of the disposal of highly radioactive waste into cosmos are reviewed. The disposal of highly radioactive waste is serious problem to be solved in the near future, because it is produced in large amounts by the reprocessing of spent fuel. The promising methods proposed are (i) underground disposal, (ii) ocean disposal, (iii) cosmic disposal and (iv) extinguishing disposal. The final disposal method is not yet decided internationally. The radioactive waste contains very long life nuclides, for example transuranic elements and actinide elements. The author thinks the most perfect and safe disposal method for these very long life nuclides is the disposal into cosmos. The space vehicle carrying radioactive waste will be launched safely into outer space with recent space technology. The selection of orbit for vehicles (earth satellite or orbit around planets) or escape from solar system, selection of launching rocket type pretreatment of waste, launching weight, and the cost of cosmic disposal were investigated roughly and quantitatively. Safety problem of cosmic disposal should be examined from the reliable safety study data in the future.

Spread-sheet application to classify radioactive material for shipment

International Nuclear Information System (INIS)

Brown, A.N.

1998-01-01

A spread-sheet application has been developed at the Idaho National Engineering and Environmental Laboratory to aid the shipper when classifying nuclide mixtures of normal form, radioactive materials. The results generated by this spread-sheet are used to confirm the proper US DOT classification when offering radioactive material packages for transport. The user must input to the spread-sheet the mass of the material being classified, the physical form (liquid or not) and the activity of each regulated nuclide. The spread-sheet uses these inputs to calculate two general values: 1)the specific activity of the material and a summation calculation of the nuclide content. The specific activity is used to determine if the material exceeds the DOT minimal threshold for a radioactive material. If the material is calculated to be radioactive, the specific activity is also used to determine if the material meets the activity requirement for one of the three low specific activity designations (LSA-I, LSA-II, LSA-III, or not LSA). Again, if the material is calculated to be radioactive, the summation calculation is then used to determine which activity category the material will meet (Limited Quantity, Type A, Type B, or Highway Route Controlled Quantity). This spread-sheet has proven to be an invaluable aid for shippers of radioactive materials at the Idaho National Engineering and Environmental Laboratory. (authors)

Determination of the nuclide vector for decommissioning projects at PSI (Paul Scherrer Institute, Switzerland)

Energy Technology Data Exchange (ETDEWEB)

Jaeggi, Maya; Eikenberg, J. [Paul Scherrer Inst. (PSI), Villigen (Switzerland). Labor fuer Radioanalytik; Ehrlicher, U. [Paul Scherrer Inst. (PSI), Villigen (Switzerland). Sektion Rueckbau und Entsorgung

2012-06-15

In the context of two reactor decommissioning projects, radioactive slurry from concrete cutting was collected in the retention pond (RHB) at the Paul Scherrer Institute, along with radioactive drain outlets. Additionally, there are active residues from former operations. The task was to determine the nuclide vector of the radioactive slurry before final disposal. Due to the slurry from neutron-activated concrete, activation products, like {sup 55}Fe, {sup 60}Co, {sup 63}Ni, {sup 133}Ba, {sup 152}Eu, {sup 154}Eu and {sup 155}Eu can be expected. Accumulated drain outlets from laboratories, where work with radioactive substances is being done, were expected to contain {sup 22}Na, {sup 60}Co, {sup 134}Cs, {sup 137}Cs, {sup 133}Ba, {sup 152}Eu, {sup 154}Eu, {sup 155}Eu, {sup 241}Am, {sup 239/240}Pu, {sup 241}Pu, {sup 244}Cm, {sup 234}U, {sup 235}U, {sup 238}U, {sup 230}Th, {sup 232}Th and {sup 90}Sr. For further clarification, {sup 3}H and {sup 14}C in the water and in the organic phase had to be measured as well. This work gives an overview about the slurry dissolution techniques, the radiochemical separation methods and activity concentrations of the nuclide vector. Further processing of the slurry is also discussed. (orig.)

Radioactive contamination of honey and other bee-keeping products

International Nuclear Information System (INIS)

Frantsevich, L.I.; Komissar, A.D.; Levchenko, I.A.

1990-01-01

Great amount of dust is collected in propolis under emergency atmospheric fallouts. Specific coefficient of the product migration amounts to several m 2 per 1 kg. Propolis is a good biological indicator of radioactive fallouts. The propolis collection is inadmissible after radioactive fallouts. Cocoon residuals obtained during bees-wax separation contain many radionuclides and should be disposed in special places. Nuclides are absent in bees-wax. Nuclides accumulated absent in a bee organism migrate into honey and queen milk, the honey is contaminated mainly via biogenic path

A concept for limiting the number of radioactive tracer experiments in a factory plant

International Nuclear Information System (INIS)

Monchy, A.R. de

1980-01-01

There are currently no restrictions regarding the quantities of radioactive material stored, used or discharged in factories where radioactive tracer experiments are performed. This article describes a concept for such restrictions, based on two criteria - 1) a system of standards for the absorption of the contamination by either water or air, dependent on the half life of the nuclides used and 2) a summation procedure of the activities of the nuclides used, the activities being weighed by the toxicity and chance of spreading of each nuclide. (C.F.)

Destructive and non-destructive tests for radioactive waste packages Task 3 Characterization of radioactive waste forms. A series of final reports (1985-89) No 43

International Nuclear Information System (INIS)

Odoj, R.

1991-01-01

On the basis of preliminary waste acceptance requirements quality control of radioactive waste has to be performed prior to interim storage or final disposal. The quality control can either be achieved by random tests on conditioned radioactive waste packages or by process qualification of the conditioning processes. One of the most important criteria is the activity of the radioactive waste product or packages. To get some first information on the waste package γ-spectrometric measurement is performed as non-destructive test. Besides the γ-emitting nuclides the α and β-emitting nuclides can be estimated by calculation if the waste was generated in nuclear power plants and the nuclide relations are known. If the non-destructive determination of nuclides is not sufficient or the non-radioactive content of the waste packages has to be identified sampling from the waste packages has to be performed. This can best be done by core drilling. To avoid the need of water for cooling the drill head, air cooled core drilling is investigated. As mixed wastes is not allowed for final disposal the determination of possible organic toxic materials like PCB, dioxin and furane-compounds in cemented wastes is conducted by GC-MS-investigations. For getting more knowledge in the field of process qualification concerning super compaction, instrumentation of the super compaction process is investigated and tested

Studies on radioactivity distribution and radioactive mineral identification in uranium ores from Espinharas (PB), Brazil

International Nuclear Information System (INIS)

Oliveira, G.N.M. de.

1979-01-01

Studies about the identification of radioactive minerals in uranium bearing rocks from Espinharas (PB), Brazil are presented. Autoradiography with α-sensitive nuclear emulsions was utilized for determining radioctivity distributions and for localizing radioactive minerals, in combination with microscopy, X-ray diffractometry, PIXE and eletron microprobe analysis for its identification. Mineralized gneisse and feldspatic rock, the two principal samples studied, show distinct differences in radioactive distribution patterns, however the main carriers for U and Th seem to be the same. Microanalysis shows that elements are associated with Si, Ca, Fe and Al an some trace elements like Y, Zr, Ti, etc. U and Th are distributed uniformly in feldspatic rock and inhomogeneously in mineralized gneisse, indicating that the zonary structure of the radioactive cristals, frequently observed in gneisse, could be due to variable U:Th ratios. Chemical analysis, X-ray diffraction datas and microscopic studies indicates that the principal carrier for radioactivity in the rocks of Espinharas is a silicate mineral of U and Th, probably situaded in the series of transition: Coffinite -> uraninite, thorogummite -> thorianite. Some additional experiments about leachability of uranium with diluted sulfuric acid are reported, which confirm the different nature of radioactivity distribution in feldspatic and gneissic rocks. (author) [pt

Radioactive nuclides formed by irradiation of the natural elements with thermal neutrons

Energy Technology Data Exchange (ETDEWEB)

Ekberg, Kim

1959-05-15

For each natural element up to Bi this report gives: the 2200 m/sec neutron absorption cross section; the nuclides formed by thermal neutron activation; the saturation activity per gram natural element for a certain flux; half life and 'tenth life' of the activity; {beta}-energy and/or type of decay; mean {gamma} energy per disintegration; energy and abundance of {gamma} quanta.

Batch Kd measurements of nuclides to estimate migration potential at the proposed Waste Isolation Pilot Plant in New Mexico

International Nuclear Information System (INIS)

Serne, R.J.; Rai, D.; Mason, M.J.; Molecke, M.A.

1977-01-01

Laboratory measurements to determine the sorption distribution coefficients, Kd, of radionuclides present in, and potentially leached from, radioactive wastes, in contact with representative geologic media, have been conducted. The nuclides studied include Cs, Sr, Tc, Ru, Sb, Ce, Eu, Pu, Np, Cm, Am, U, and Pa. The crushed rock materials used were from the vicinity of the Waste Isolation Pilot Plant, a project to isolate radioactive wastes in a bedded salt facility, near Carlsbad, New Mexico. Solutions used consist of salt brine and groundwater, specific to the WIPP site, plus distilled water, for laboratory intercomparisons. The batch Kd data reported, plus data from sorption and migration measurements being conducted or planned elsewhere, will be used to evaluate the potential for radionuclide migration from the bedded salt WIPP facility. The data can be used for transport modeling and for safety assessment determinations

Radioactivity in mushrooms in northeast Italy following the Chernobyl accident

International Nuclear Information System (INIS)

Battiston, G.A.; Degetto, S.; Gerbasi, R.; Sbrignadello, G.

1989-01-01

Radionuclide activities in common edible mushrooms, collected in northeast Italy following the Chernobyl accident, are reported. The highest levels were found in Clitocybe infundibuliformis, Cantharellus lutescens and Boletus cavipes. In addition, a large number of soil samples was collected in the same area. From the 137 Cs/ 134 Cs ratios, its was possible to differentiate the radiocesium contribution from pre-Chernobyl fallout in both fungi and soil. The contour maps for 137 Cs and 134 Cs distributions are reported. The radioactivity detected in the mushrooms is not related in a simple manner to the contamination level of the corresponding soil. Some species tend to concentrate cesium and silver nuclides, whilst others show little affinity for these and other nuclides. Explanations for the different behavioral characteristics of the species are suggested. (author)

Monitoring of Radio-nuclides in the Vicinities of Finnish Nuclear Power Plants in 2002-2004

International Nuclear Information System (INIS)

Ilus, E.; Klemola, S.; Vartti, V.-P.; Mattila, J.; Ikaeheimonen, T.K.

2000-03-01

The monitoring of radioactive substances round Finnish nuclear power plants continued in 2002-2004 in accordance with the regular environmental monitoring programmes. Altogether, some 1000 samples are analysed annually from the terrestrial and aquatic environs of the two power plants. Trace amounts of activation products originating from airborne releases from the local power plants were detected in several air and deposition samples taken from the close vicinities of the power plants. At Loviisa, observations were made in two; at Olkiluoto in three aerosol samples during the reporting period. Except for the naturally occurring beryllium-7, the concentrations of all radionuclides in the air samples were very low; from few microbequerels to few tens of microbequerels per cubic metre. A similar pattern was tenable for the deposition samples as well. The activity concentrations of cobalt-60 of local origin were at their highest 0.3 bequerels per square metre in one sample taken from Loviisa and in one sample taken from Olkiluoto. No traces of local discharge nuclides were detected in foodstuffs, drinking water or garden products. In mushrooms and wild berries picked up in 2004 from the Loviisa area, only Chernobyl-derived caesium isotopes and natural potassium-40 were detected. Local discharge nuclides were more abundant in the aquatic environment, especially in samples of indicator organisms, sinking matter and sediments, which effectively accumulate radioactive substances. Besides tritium originating from local discharges, the most significant artificial radionuclide in the samples taken from the aquatic environs of the power plants was still caesium-137 originating from the Chernobyl accident (potassium-40 is a naturally occurring radionuclide). Elevated tritium concentrations were more frequent in the water samples from Loviisa. In indicator organisms and sinking matter, the observed concentrations of local discharge nuclides were generally somewhat higher and

Survey monitoring of environmental radioactivity in Gunsan area

Energy Technology Data Exchange (ETDEWEB)

Kim, Byoung Ho; Ro, Jeong Suk [Kunsan Regional Radioactivity Monitoring Station, Gunsan (Korea, Republic of)

2001-01-15

At Regional Radioactivity Monitoring Station in Kunsan have been measured priodically in 2000 gross beta activities in the airborne dust, fallout, precipitation and tap water and gamma exposure rates. Artificial radionuclide of {sup 137}Cs in airborne dust, fallout and precipitation have also been monitored at the station. As a part of environmental radiation/radioactivity distribution survey around Jeon-buk, vegetables, fishes, shellfishes, drinking water (total 33ea) samples were taken from sampling sites which were selected by KINS. We analysis gamma isotope for all. No significant Changes from the previous survey have been found in both beta activities and gamma exposure rates. As the results of analyzig an artificial nuclide concentration in living environmental sample in Jeon-buk are I fee of radiological contaminants.

Survey monitoring of environmental radioactivity in Gunsan area

Energy Technology Data Exchange (ETDEWEB)

Kim, Byoung Ho; Ro, Jeong Suk [Kunsan Regional Radioactivity Monitoring Station, Gunsan (Korea, Republic of)

2002-12-15

At Regional Radioactivity Monitoring Station in Kunsan have been measured priodically in 2002 gross beta activities in the airborne dust, fallout, precipitation and tap water and gamma exposure rates. Artificial radionuclide of {sup 137}Cs in airborne dust, fallout and precipitation have also been monitored at the station. As a part of environmental radiation/radioactivity distribution survey around Jeon-buk, vegetables, fishes, shellfishes, drinking water (total 33ea) samples were taken from sampling sites which were selected by KINS. We analysis gamma isotope for all. No significant changes from the previous survey have been found in both beta activities and gamma exposure rates. As the results of analyzig an artificial nuclide concentration in living environmental sample in Jeon-buk are fee of radiological contaminants.

Survey monitoring of environmental radioactivity in Gunsan area

International Nuclear Information System (INIS)

Kim, Byoung Ho; Ro, Jeong Suk

2002-12-01

At Regional Radioactivity Monitoring Station in Kunsan have been measured priodically in 2002 gross beta activities in the airborne dust, fallout, precipitation and tap water and gamma exposure rates. Artificial radionuclide of 137 Cs in airborne dust, fallout and precipitation have also been monitored at the station. As a part of environmental radiation/radioactivity distribution survey around Jeon-buk, vegetables, fishes, shellfishes, drinking water (total 33ea) samples were taken from sampling sites which were selected by KINS. We analysis gamma isotope for all. No significant changes from the previous survey have been found in both beta activities and gamma exposure rates. As the results of analyzig an artificial nuclide concentration in living environmental sample in Jeon-buk are fee of radiological contaminants

Radioactive nuclides formed by irradiation of the natural elements with thermal neutrons

Energy Technology Data Exchange (ETDEWEB)

Ekberg, Kim

1959-05-15

For each natural element up to Bi this report gives: the 2200 m/sec neutron absorption cross section; the nuclides formed by thermal neutron activation; the saturation activity per gram natural element for a certain flux; half life and 'tenth life' of the activity; {beta}-energy and/or type of decay; mean {gamma} energy per disintegration; energy and abundance of {gamma} quanta.

Distribution of natural occurring radionuclide in some industral residues used in new type wall materials

International Nuclear Information System (INIS)

Chen Yingmin; Li Fusheng; Xu Jiaang; Deng Daping; Yuan Ming; Ma Shi; Chen Yue

2006-01-01

Objective: To study the natural radioactive nuclide distribution characteristic of fly ash, gangue and various kinds of slag used in the new-type wall material and offer scientific basis for reducing the radiation dosage that the public suffers. Methods: The activity concentrations of the contents of natural radioactive nuclides of different industral waste residues have been determined by HPGe gamma-ray spectrometry. Results: The mean Raeq is successively fly ash (279.13 Bq kg -1 ), slag (225.69 Bq kg -1 ), gangue (141.26 Bq kg -1 ) from high to low and all of the samples is lower than the limit set in the OECD. The arithmetic mean activities of 236 Ra, 232 Th, 40 K in fly-ash samples are 127.88, 93.83, 221.75 Bq kg -1 ; for coal slag samples are 73.89, 97.13, 283.44 Bq kg -1 and for coal gangue samples are 47.85, 45.21, 413.56 Bq kg -1 . For the same power plant, the radioactive nuclide activity of the fly ash gathered in different time may have very great differences, the maximum can reach more than 2 times of the minimum. Conclusion: the fly ash and slag should be controlled strictly on rational proportion, which should not exceed 70% of the total mass. The mixing of the average radioactive level of the gangue is nearly equal that of to clay, it can be unrestricted in the mixing proportion in process of production. The manufacturer of new-type wall materials should often measure the radioactive level of the industrial waste residue in production. Make the content of radioactive nuclide in the products reach the rational level as low as possible. (authors)

Radioactivity in food crops

Energy Technology Data Exchange (ETDEWEB)

Drury, J.S.; Baldauf, M.F.; Daniel, E.W.; Fore, C.S.; Uziel, M.S.

1983-05-01

Published levels of radioactivity in food crops from 21 countries and 4 island chains of Oceania are listed. The tabulation includes more than 3000 examples of 100 different crops. Data are arranged alphabetically by food crop and geographical origin. The sampling date, nuclide measured, mean radioactivity, range of radioactivities, sample basis, number of samples analyzed, and bibliographic citation are given for each entry, when available. Analyses were reported most frequently for /sup 137/Cs, /sup 40/K, /sup 90/Sr, /sup 226/Ra, /sup 228/Ra, plutonium, uranium, total alpha, and total beta, but a few authors also reported data for /sup 241/Am, /sup 7/Be, /sup 60/Co, /sup 55/Fe, /sup 3/H, /sup 131/I, /sup 54/Mn, /sup 95/Nb, /sup 210/Pb, /sup 210/Po, /sup 106/Ru, /sup 125/Sb, /sup 228/Th, /sup 232/Th, and /sup 95/Zr. Based on the reported data it appears that radioactivity from alpha emitters in food crops is usually low, on the order of 0.1 Bq.g/sup -1/ (wet weight) or less. Reported values of beta radiation in a given crop generally appear to be several orders of magnitude greater than those of alpha emitters. The most striking aspect of the data is the great range of radioactivity reported for a given nuclide in similar food crops with different geographical origins.

Results of radioactivity surveys in Miyagi Prefecture

International Nuclear Information System (INIS)

1983-01-01

The results of radioactivity surveys carried out in Miyagi Prefecture in fiscal 1981 (from April, 1981, to March, 1982), entrusted by the Science and Technology Agency, are presented in tables: total β radioactivity in rainwater, in rainwater and dust collected by large basins, in daily foods, in land water, in dairy products and vegetables, in marine products and in soil, 131 I nuclide in cow's milk, air γ-ray dose rate by survey meters, and air γ-ray counting, rate by a monitoring post were examined. The total β radioactivity was measured by a GM counting apparatus with an automatic sample changer, the nuclide analysis by a NaI(Tl) scintillation spectrometer, the air γ-ray dose rate by a NaI(Tl) scintillation survey meter, and the γ-ray counting rate by a NaI(Tl) scintillation type monitoring post. (Mori, K.)

Radioactive Environment Contamination and Abilities of the Modern Radiochemistry in the Field of Nuclear Waste Disposal and Monitoring

International Nuclear Information System (INIS)

Myasoedov, B.F.; Novikov, A.P.

1999-01-01

The study of environmental contamination caused by anthropogenic impacts and, primarily, by radioactive nuclides is one of the main scientific problems facing contemporary science. This is known as Radioecological monitoring. Decisions regarding the remediation of polluted areas require detailed information about the distribution of radioactive nuclides in terrestrial and aquatic ecosystems, as well as, knowledge about radionuclides occurrence forms and migration patterns. Different sources of radionuclides penetration into the environment appoint their interaction with nature matrices in different ways and should be considered accordingly. An overview is given of the present radioecological situation around the reprocessing plant M ayak , which was constructed more than 40 years ago for the production of plutonium for military purposes. Some new approaches, methods and tools developed at the Vernadsky Institute of Geochemistry and Analytical Chemistry for the isolation, concentration and determination of radionuclides in various environmental samples are discussed. Data regarding the distribution, occurrence, and migration processes of radionuclides 90 Sr, 137 Cs, 239 Pu and 241 Am, in aquatic and terrestrial ecosystems of the impact zone of the Mayak plant, are presented

The nuclide inventory in SFR-1

International Nuclear Information System (INIS)

Ingemansson, Tor

2001-10-01

This report is an account for a project carried out on behalf of the Swedish Radiation Protection Authority (SSI): 'Nuclide inventory in SFR-1' (The Swedish underground disposal facility for low and intermediate level reactor waste). The project comprises the following five sub-projects: 1) Measuring methods for nuclides, difficult to measure, 2) The nuclide inventory in SFR-1, 3) Proposal for nuclide library for SFR-1 and ground disposal, 4) Nuclide library for exemption, and 5) Characterising of the nuclide inventory and documentation for SFL waste. In all five sub-projects long-lived activity, including Cl-36, has been considered

Predicting Induced Radioactivity at High Energy Accelerators

Energy Technology Data Exchange (ETDEWEB)

Fasso, Alberto

1999-08-27

Radioactive nuclides are produced at high-energy electron accelerators by different kinds of particle interactions with accelerator components and shielding structures. Radioactivity can also be induced in air, cooling fluids, soil and groundwater. The physical reactions involved include spallations due to the hadronic component of electromagnetic showers, photonuclear reactions by intermediate energy photons and low-energy neutron capture. Although the amount of induced radioactivity is less important than that of proton accelerators by about two orders of magnitude, reliable methods to predict induced radioactivity distributions are essential in order to assess the environmental impact of a facility and to plan its decommissioning. Conventional techniques used so far are reviewed, and a new integrated approach is presented, based on an extension of methods used at proton accelerators and on the unique capability of the FLUKA Monte Carlo code to handle the whole joint electromagnetic and hadronic cascade, scoring residual nuclei produced by all relevant particles. The radiation aspects related to the operation of superconducting RF cavities are also addressed.

Separation of actinides and long-lived fission products from high-level radioactive wastes (a review)

International Nuclear Information System (INIS)

Kolarik, Z.

1991-11-01

The management of high-level radioactive wastes is facilitated, if long-lived and radiotoxic actinides and fission products are separated before the final disposal. Especially important is the separation of americium, curium, plutonium, neptunium, strontium, cesium and technetium. The separated nuclides can be deposited separately from the bulk of the high-level waste, but their transmutation to short-lived nuclides is a muchmore favourable option. This report reviews the chemistry of the separation of actinides and fission products from radioactive wastes. The composition, nature and conditioning of the wastes are described. The main attention is paid to the solvent extraction chemistry of the elements and to the application of solvent extraction in unit operations of potential partitioning processes. Also reviewed is the behaviour of the elements in the ion exchange chromatography, precipitation, electrolysis from aqueous solutions and melts, and the distribution between molten salts and metals. Flowsheets of selected partitioning processes are shown and general aspects of the waste partitioning are shortly discussed. (orig.) [de

Distribution measurement of 60Co target radioactive specific activity

International Nuclear Information System (INIS)

Li Xingyan; Chen Zigen; Ren Min

1994-01-01

Radioactive specific activity distribution of cobalt 60 target by irradiation in HFETR is a key parameter. With the collimate principle, the under water measurement device and conversion coefficient which is get by experiments, and the radioactive specific activity distribution is obtained. The uncertainty of measurement is less than 10%

Radioactivity standards distribution program, 1978--1979. Interim report, 1978--1979

International Nuclear Information System (INIS)

Ziegler, L.H.

1978-06-01

A program for the distribution of calibrated radioactive samples, as one function of EPA's quality assurance program for environmental radiation measurements, is described. Included is a discussion of the objectives of the distribution program and a description of the preparation, availability, and distribution of calibrated radioactive samples. Instructions and application forms are included for laboratories desiring to participate in the program. This document is not a research report. It is designed for use by personnel of laboratories participating or desiring to participate in the Radioactivity Standards Distribution Program, which is a part of the U.S. Environmental Protection Agency's quality assurance program

Capturing device for radioactive corrosion products

International Nuclear Information System (INIS)

Ono, Kiyoshi.

1987-01-01

Purpose: To render the flow channel area uniform for each of coolants over the entire capturing device and reduce the corrosion of capturing materials due to coolants. Constitution: Most of radioactivity caused by radioactive corrosion products are due to Mn-54 radioactive nuclides and it has been known that the nuclides are readily deposited to the surface of nickel material in sodium at high temperature. It is difficult in a conventional capturing device constituted by winding a nickel plate fabricated with protrusions in a multiple-coaxial configuration, that the flow channel area is reduced in a portion of the flow channel and it is difficult to make the flow of the coolants uniform. In view of the above, by winding a nickel plate having a plurality of protrusions at the surface formed integrally by way of an electrolytic process into a multiple-coaxial or spiral shape, those having high resistance to the coolant corrosion can be obtained. (Takahashi, M.)

Comparison measure of natural radioactivity in environment specimen using HPGe and NaI(Tl) γ-ray spectrometer

International Nuclear Information System (INIS)

Zhou Chunlin; Han Feng; Li Tiantuo; Ma Wenyan; Di Yuming; Guo Huiping; Wu Yuelei

2000-01-01

The author reports the comparison results on natural radioactive nuclide contents of soil specimen from an uranium diggings with HPGe and NaI(Tl) γ-ray spectrometer. Relative method and athwart matrix method are used to analyze natural radioactive nuclide contents in samples of soil. The results are compared and are proven to be in accordance with each other

Production and Separation of T = 1/2 Nuclides for {beta}--{nu} angular correlation measurements

Energy Technology Data Exchange (ETDEWEB)

Delahaye, P.; Bajeat, O.; Saint Laurent, M. G.; Thomas, J. C.; Traykov, E. [GANIL, CEA/DSM-CNRS/IN2P3, Bd. Becquerel, BP 55027, 14076 CAEN Cedex 05 (France); Couratin, C. [GANIL, CEA/DSM-CNRS/IN2P3, Bd. Becquerel, BP 55027, 14076 CAEN Cedex 05 (France); LPC Caen, 6 bd Marechal Juin, 14050 CAEN Cedex (France); Lienard, E.; Ban, G.; Durand, D.; Flechard, X. [LPC Caen, 6 bd Marechal Juin, 14050 CAEN Cedex (France); Naviliat-Cuncic, O. [NSCL, Michigan State University, 1 Cyclotron, East Lansing, Michigan 48824-1321 (United States); Stora, T. [ISOLDE, CERN, 1211 Geneva 23 (Switzerland); Collaboration: GANISOL Group

2011-11-30

The SPIRAL facility at GANIL, which uses the so-called ISOL method to produce radioactive ion beams, is being upgraded to extend its production capabilities to the metallic beams of neutron deficient isotopes. We discuss here the potentialities offered by this upgrade for the measurement of the {beta}--{nu} angular correlation in the {beta}--decay of mirror nuclides.

Progress report on safety research on radioactive waste management for the period April 1992 to March 1993

International Nuclear Information System (INIS)

Muraoka, Susumu; Senoo, Muneaki; Sekine, Keiichi

1994-03-01

This report summarizes the research and development activities on radioactive waste management at the Engineered Barrier Materials Laboratory, Shallow Land Migration Laboratory, Environmental Geochemistry Laboratory and Environmental Radiochemistry Laboratory of the Department of Environmental Safety Research during the fiscal year of 1992 (April 1, 1992-March 31, 1993). The topics are as follows: 1) As for waste forms and engineered barrier material, performance assessment studies were carried out on various waste forms, buffer materials and mortar. 2) In the safety evaluation study for shallow land disposal, migration behavior in the soil layer were studied. 3) In the safety evaluation study for geological disposal, chemical behavior of nuclide in water, nuclide migration and fixation in geosphere were studied. 4) Distribution of uranium and migration of uranium series nuclide in uranium ore were examined as a natural analogue study. (author)

The stochastic nuclide transport model for buffer/backfill materials

International Nuclear Information System (INIS)

Ma Liping; Han Yongguo

2014-01-01

Currently, study on nuclide migration law in geological disposal repository of high level waste is assumed buffer/backfill layer to be continuous medium, utilized the continuity equation, equation of state, the equations of motion, etc, formed a set of theory and method to estimate nuclide concentration distribution in buffer/backfill layer, and provided an important basis for nuclide migration rules of repository. However, it is necessary to study the buffer/backfill layer microstructure and subtly describe the pore structure and fracture system of the buffer/backfill layer, and reflect the changes in connectivity and in different directions of the buffer/backfill layer. Through using random field theory, the nuclide transport for the buffer/backfill layer in geological disposal repository of nuclear waste is described in the paper. This paper mainly includes that, t represents the time, ξ t ⊂ Z d = d represents the integer lattice, Z represents collectivity integers, d = l, 2, 3, for instance, d = 2, Z d = {(m, n) : m, n ∈ Z} the state point of ξ t is typically considered to be occupied by the nuclide concentration values of the buffer/backfill layer, ξ t also represents random set in the diagram of two dimensional integer lattice, namely, t ∈ [0, T], {ξ t ,0 ≤ t ≤ ⊂ T} Consequently, according to the stochastic process obtained above, the changes of the nuclide concentration values of the buffer/backfill layer or the buffer/backfill laboratory materials in the repository with the time can be known. (authors)

Development of carrier usage for the treatment of radioactive effluent

International Nuclear Information System (INIS)

Kahraman, A.

1997-01-01

Low level radioactive liquid wastes are produced in many nuclear applications. Their physico-chemical characteristics may very considerably. Chemical precipitation is a convenient treatment method for the liquid streams of high salinity or solid content containing different radionuclide types. Generally, the concentrations of nuclides in liquid wastes are extremely low. For example, 1000 Bq of 137 Cs makes about 3·10 -10 g of caesium. Therefore conventional precipitation cannot be applied since the solubility product value is not exceeded. The carriers which are capable to adsorb the nuclides are used to achieve the nuclide removal. Stable isotopes of the nuclide are usually added as the carriers but any reagent which has similar chemical specifications with the nuclide can also be used as the carrier. Precipitation of these non-radioactive carriers ion together with the radionuclide is called co-precipitation. The operational steps of the chemical precipitation process should be established and applied in a treatment facility. Thus, the most suitable carrier for a particular nuclide and its usage conditions are required to be determined. In this study, the carriers for removal of 137 Cs and uranium, their accurate amounts and usage conditions to achieve highest decontamination factors (DF) have been investigated. Residual sludge volumes were evaluated for cementation purposes. The cement composite samples were prepared for each set of experiments and hardening times were measured. 9 refs, 9 figs

Uptake of nuclides by plants

International Nuclear Information System (INIS)

Greger, Maria

2004-04-01

This review on plant uptake of elements has been prepared to demonstrate how plants take up different elements. The work discusses the nutrient elements, as well as the general uptake and translocation in plants, both via roots and by foliar absorption. Knowledge of the uptake by the various elements within the periodic system is then reviewed. The work also discusses transfer factors (TF) as well as difficulties using TF to understand the uptake by plants. The review also focuses on species differences. Knowledge necessary to understand and calculate plant influence on radionuclide recirculation in the environment is discussed, in which the plant uptake of a specific nuclide and the fate of that nuclide in the plant must be understood. Plants themselves determine the uptake, the soil/sediment determines the availability of the nuclides and the nuclides themselves can interact with each other, which also influences the uptake. Consequently, it is not possible to predict the nuclide uptake in plants by only analysing the nuclide concentration of the soil/substrate

Uptake of nuclides by plants

Energy Technology Data Exchange (ETDEWEB)

Greger, Maria [Stockholm Univ. (Sweden). Dept. of Botany

2004-04-01

This review on plant uptake of elements has been prepared to demonstrate how plants take up different elements. The work discusses the nutrient elements, as well as the general uptake and translocation in plants, both via roots and by foliar absorption. Knowledge of the uptake by the various elements within the periodic system is then reviewed. The work also discusses transfer factors (TF) as well as difficulties using TF to understand the uptake by plants. The review also focuses on species differences. Knowledge necessary to understand and calculate plant influence on radionuclide recirculation in the environment is discussed, in which the plant uptake of a specific nuclide and the fate of that nuclide in the plant must be understood. Plants themselves determine the uptake, the soil/sediment determines the availability of the nuclides and the nuclides themselves can interact with each other, which also influences the uptake. Consequently, it is not possible to predict the nuclide uptake in plants by only analysing the nuclide concentration of the soil/substrate.

Observation of environmental radioactivity at definite time and definite point

International Nuclear Information System (INIS)

Inokoshi, Yukio; Fukuchi, Ryoichi; Irie, Takayuki; Hosoda, Nagako; Okano, Yasuhiro; Shindo, Koutaro

1990-01-01

The measurement of environmental radioactivity in Tokyo Metropolis was carried out. The objects of measurement were rainwater, atmospheric floating dusts, spatial dose and the activated sludge in sewage treatment plants. Rainwater, atmospheric floating dusts and spatial dose were analyzed mainly considering radioactive fallout, and activated sludge was analyzed mainly considering radioactive medical matters. For the analysis of nuclides, a Ge(Li) semiconductor detector was used, and spatial dose rate was measured with a DBM type dose rate meter. In activated sludge, the nuclides used for radioactive medicines were found, but in rainwater, atmospheric floating dusts and spatial dose, particular abnormality was not found. The objective of this investigation is to collect over long period at definite time and definite points the data on environmental radioactivity in Tokyo, thus to grasp the level of normal values, and in abnormal case, to clarify the cause and to evaluate the exposure dose. The instruments used, the method of measuring each object and the results are reported. (K.I.)

SGSreco. A method for accurate and reliable determination of the radioactive inventory in radioactive waste barrels; SGSreco. Eine Methode zur genauen und verlaesslichen Bestimmung des Aktivitaetsinventares in radioaktiven Abfallfaessern

Energy Technology Data Exchange (ETDEWEB)

Krings, Thomas; Mauerhofer, Eric [Forschungszentrum Juelich GmbH (Germany). Inst. fuer Energie und Klimaforschung (IEK), Nukleare Entsorgung und Reaktorsicherheit (IEK-6)

2013-07-01

The computer code SGSreco is used for the evaluation of counting rate distributions from SGS (segmented gamma scan) measurements on radioactive waste barrels. The code is based on data fitting to a physical model function; the results include position parameters, point source activities and the activity of a homogeneous activity distribution. A simulation study has shown that the point source activity can be determined with 2% accuracy. Conventional methods are based on the assumption of a homogeneous activity distribution which is wrong for about 75% of the radioactive waste barrels, the determined nuclide specific activities have significant error rates. The use of SGSreco improves the accuracy and reliability of activity determinations and reduces the conservatism of activity estimations. The latter one allows an optimal utilization of the repository capacity with respect to the maximum activities at the end of the operational phase of the repository Konrad.

On risk assessment of high level radioactive waste disposal

International Nuclear Information System (INIS)

Smith, C.F.; Kastenberg, W.E.

1976-01-01

One of the major concerns with the continued growth of the nuclear power industry is the production of the high level radioactive wastes. The risks associated with the disposal of these wastes derives from the potential for release of radioactive materials into the environment. The development of a methodology for risk analysis is carried out. The methodology suggested involves the probabilistic analysis of a general accident consequence distribution. In this analysis, the frequency aspect of the distribution is treated separately from the normalized probability function. In the final stage of the analysis, the frequency and probability characteristics of the distribution are recombined to provide an estimate of the risk. The characterization of the radioactive source term is accomplished using the ORIGEN computer code. Calculations are carried out for various reactor types and fuel cycles, and the overall waste hazard for a projected 35 year nuclear power program is determined. An index of relative nuclide hazard appropriate to problems involving the management of high level radioactive wastes is developed. As an illustration of the methodology, risk analyses are made for two proposed methods for waste management: extraterrestrial disposal and interim surface storage. The results of these analyses indicate that, within the assumptions used, the risks of these management schemes are small compared with natural background radiation doses. (Auth.)

Natural radioactivity distribution images and their educational uses

International Nuclear Information System (INIS)

Mori, Chizuo; Sumi, Tetsuo; Miyahara, Hiroshi; Uritani, Akira; Nishina, Kojiro

1999-01-01

Distribution images of natural radioactivities in vegetables, meat and porcelain works were obtained by use of Imaging Plate with very high sensitivity to radiations. A brochure titled 'Natural Radiations through Naked Eyes' was published in both Japanese and English which included the images mentioned above. In this paper, the method to obtain the distribution images of extremely low level natural radioactivity, the content of the brochure and the effect of it to the public are described. (author)

Natural radioactivity distribution images and their educational uses

Energy Technology Data Exchange (ETDEWEB)

Mori, Chizuo; Sumi, Tetsuo [Aichi Institute of Technology, Toyota, Aichi (Japan); Miyahara, Hiroshi; Uritani, Akira; Nishina, Kojiro

1999-09-01

Distribution images of natural radioactivities in vegetables, meat and porcelain works were obtained by use of Imaging Plate with very high sensitivity to radiations. A brochure titled 'Natural Radiations through Naked Eyes' was published in both Japanese and English which included the images mentioned above. In this paper, the method to obtain the distribution images of extremely low level natural radioactivity, the content of the brochure and the effect of it to the public are described. (author)

Radioactive Aerosol Size Distribution Measured in Nuclear Workplaces

International Nuclear Information System (INIS)

Kravchik, T.; Oved, S.; German, U.

2002-01-01

Inhalation is the main route for internal exposure of workers to radioactive aerosols in the nuclear industry.Aerosol's size distribution and in particular its activity median aerodynamic diameter (AMAD)is important for determining the fractional deposition of inhaled particles in the respiratory tract and the resulting doses. Respiratory tract models have been published by the International Commission on radiological Protection (ICRP).The former model has recommended a default AMAD of 1 micron for the calculation of dose coefficients for workers in the nuclear industry [1].The recent model recommends a 5 microns default diameter for occupational exposure which is considered to be more representative of workplace aerosols [2]. Several researches on radioactive aerosol's size distribution in nuclear workplaces has supported this recommendation [3,4].This paper presents the results of radioactive aerosols size distribution measurements taken at several workplaces of the uranium production process

Environmental safety evaluation in test sea disposal of low-level radioactive wastes

International Nuclear Information System (INIS)

1979-01-01

The study results on the environmental safety in the test sea disposal of low-level wastes by Subcommittee on Radioactive Waste Safety Technology in Nuclear Safety Commission are given in connection with the test disposal of radioactive wastes into sea reported by the Nuclear Safety Bureau. The Subcommittee concludes that the effect of the test disposal of radioactive wastes into sea on the environment is extremely small. The contents are as follows. The full text of the report; attached data, (1) prediction of the concentrations of radioactive nuclides in sea, (2) calculation of the concentrations of radioactive nuclides in marine life with biological paths, and (3) estimation of exposure dose in general people; references (1) radiation exposure of the personnel engaged in sea disposal, (2) the effect of a sea disaster during ocean transport. (J.P.N.)

Cosmogenic nuclides in the Martian surface: constraints for sample recovery and transport

International Nuclear Information System (INIS)

Englert, P.A.J.

1988-01-01

Stable and radioactive cosmogenic nuclides and radiation damage effects such as cosmic ray tracks can provide information on the surface history of Mars. A recent overview on developments in cosmogenic nuclide research for historical studies of predominantly extraterrestrial materials was published previously. The information content of cosmogenic nuclides and radiation damage effects produced in the Martian surface is based on the different ways of interaction of the primary galactic and solar cosmic radiation (GCR, SCR) and the secondary particle cascade. Generally the kind and extent of interactions as seen in the products depend on the following factors: (1) composition, energy and intensity of the primary SCR and GCR; (2) composition, energy and intensity of the GCR-induced cascade of secondary particles; (3) the target geometry, i.e., the spatial parameters of Martian surface features with respect to the primary radiation source; (4) the target chemistry, i.e., the chemical composition of the Martian surface at the sampling location down to the minor element level or lower; and (5) duration of the exposure. These factors are not independent of each other and have a major influence on sample taking strategies and techniques

A non-fickian approach to the consequences of dumping solid radioactive wastes in a finite ocean

International Nuclear Information System (INIS)

Sarma, T.P.; D'Souza, R.S.; Sastry, V.N.; Soman, S.D.

1981-01-01

A mathematical model is developed to describe the spatial and temporal distributions of radionuclides released from solid wastes dumped on a sea bed. It takes into account the field tested dependence of horizontal eddy diffusion coefficients by the '4/3 power law' and the geochemical mean residence times of these elements in oceans. Since ocean dimensions cannot be considered infinite except for very short lived nuclides (a few months), the reflections of nuclides at the boundaries and the consequent effects on the overall concentrations have been assessed. The computations indicate that the entire activity is confined to the ocean dimensions, and the integral mean concentration value over the entire depth approaches the well-mixed value at large times. The effect of using the geochemical residence time concept leads to much lower concentration levels in waters for transuranic nuclides such as 239 Pu because of the much shorter geochemical residence times compared to the physical half-lives; in contrast for the majority of the other nuclides, the governing factor is essentially the radioactive decay only. (author)

600 MeV Simulation of the Production of Cosmogenic Nuclides in Meteorites by Galactic Protons

CERN Multimedia

2002-01-01

A large variety of stable and radioactive nuclides is produced by the interaction of solar and galactic cosmic rays with extraterrestrial matter. Measurements of such cosmogenic nuclides provide information about the constancy of cosmic ray fluxes in space and time and about the irradiation history of individual extraterrestrial objects provided that there exist reliable models describing the production process. For the calculation of the depth dependent production of cosmogenic nuclides in meteorites no satisfactory Therefore, the irradiation of small stony meteorites (radii~$<$~40~cm) by galactic protons is simulated in a series of thick target irradiation experiments at the 600~MeV proton beam of the SC. \\\\ \\\\ The thick targets are spheres (R = 5, 15, 25 cm) and are made out of diorite because of its low water content, its high density (3.0~g/cm|3) and because it provides a good approximation of the chemical composition of some common meteorite clas These spheres will also contain a wide variety of pure...

Distribution of Pa-231 and Ra-226 in rock. An indicator of rock matrix diffusion

International Nuclear Information System (INIS)

Saarinen, L.; Suksi, J.

1995-01-01

Distribution of Ra-226 and Pa-231 in rock has been studied to find signatures that may be attributed to diffusion. The idea of studying these nuclides originated from the need to obtain interpretative support to the findings of U movement in rock. Concentration profiles of Ra-226 and Pa-231 with other U series nuclides were measured across the secondary U accumulations observed in altered rock close to a fracture in the vicinity of U deposit, and in a radioactivity anomaly. (27 refs., 10 figs., 2 tabs.)

Radioactive dust from No. 5 Fukuryu Maru

Energy Technology Data Exchange (ETDEWEB)

Yamatera, H

1954-01-01

Analysis of radioactive dust collected on board No. 5 Fukuryu Maru were done by chemical separation and measurement of ..gamma..-ray energy and half-life of each species. Results are summarized as follows, radioactive nuclide and approximate percentage of radioactivity given: /sup 103/Ru, 4.3 to 57; /sup 106/Ru, 1.4; /sup 129/Te, 1.3; /sup 131/I, 4.5; /sup 132/I, 1.0; /sup 132/Te, 1.0; etc.

Karlsruhe nuclide chart - new 9. edition 2015

Energy Technology Data Exchange (ETDEWEB)

Soti, Zsolt [European Commission, Joint Research Centre (JRC), Institute for Transuranium Elements (ITU), Postfach 2340, DE-76125 Karlsruhe, (Germany); Magill, Joseph; Pfennig, Gerda; Derher, Raymond [Nucleonica GmbH, c/o European Commission, Postfach 2340, DE-76125 Karlsruhe, (Germany)

2015-07-01

Following the success of the 8. Edition of the Karlsruhe Nuclide Chart 2012, a new edition is planned for 2015. Since the 2012 edition, more than 100 nuclides have been discovered and about 1400 nuclides have been updated. In summary, the new 9. edition contains decay and radiation data on approximately 3230 ground state nuclides and 740 isomers from 118 chemical elements. The accompanying booklet provides a detailed explanation of the nuclide box structure used in the Chart. An expanded section contains many additional nuclide decay schemes to aid the user to interpret the highly condensed information in the nuclide boxes. The booklet contains - in addition to the latest values of the physical constants and physical properties - a periodic table of the elements, tables of new and updated nuclides, and a difference chart showing the main changes in the Chart graphically. (authors)

Karlsruhe nuclide chart - new 9. edition 2015

International Nuclear Information System (INIS)

Soti, Zsolt; Magill, Joseph; Pfennig, Gerda; Derher, Raymond

2015-01-01

Following the success of the 8. Edition of the Karlsruhe Nuclide Chart 2012, a new edition is planned for 2015. Since the 2012 edition, more than 100 nuclides have been discovered and about 1400 nuclides have been updated. In summary, the new 9. edition contains decay and radiation data on approximately 3230 ground state nuclides and 740 isomers from 118 chemical elements. The accompanying booklet provides a detailed explanation of the nuclide box structure used in the Chart. An expanded section contains many additional nuclide decay schemes to aid the user to interpret the highly condensed information in the nuclide boxes. The booklet contains - in addition to the latest values of the physical constants and physical properties - a periodic table of the elements, tables of new and updated nuclides, and a difference chart showing the main changes in the Chart graphically. (authors)

A study on the stochastic model for nuclide transport in the fractured porous rock using continuous time Markov process

International Nuclear Information System (INIS)

Lee, Youn Myoung

1995-02-01

As a newly approaching model, a stochastic model using continuous time Markov process for nuclide decay chain transport of arbitrary length in the fractured porous rock medium has been proposed, by which the need for solving a set of partial differential equations corresponding to various sets of side conditions can be avoided. Once the single planar fracture in the rock matrix is represented by a series of finite number of compartments having region wise constant parameter values in them, the medium is continuous in view of various processes associated with nuclide transport but discrete in medium space and such geologic system is assumed to have Markov property, since the Markov process requires that only the present value of the time dependent random variable be known to determine the future value of random variable, nuclide transport in the medium can then be modeled as a continuous time Markov process. Processes that are involved in nuclide transport are advective transport due to groundwater flow, diffusion into the rock matrix, adsorption onto the wall of the fracture and within the pores in the rock matrix, and radioactive decay chain. The transition probabilities for nuclide from the transition intensities between and out of the compartments are represented utilizing Chapman-Kolmogorov equation, through which the expectation and the variance of nuclide distribution for each compartment or the fractured rock medium can be obtained. Some comparisons between Markov process model developed in this work and available analytical solutions for one-dimensional layered porous medium, fractured medium with rock matrix diffusion, and porous medium considering three member nuclide decay chain without rock matrix diffusion have been made showing comparatively good agreement for all cases. To verify the model developed in this work another comparative study was also made by fitting the experimental data obtained with NaLS and uranine running in the artificial fractured

Method of processing radioactive liquid wastes by using zeolites

Energy Technology Data Exchange (ETDEWEB)

Kanno, T; Mimura, H

1975-09-18

The object is to processing radioactive liquid waste by zeolites to be fixed to a solidified body having a very small lixiviation property. The nuclide in radioactive liquid waste is exchanged and adsorbed into natural or synthetic zeolites, which are then burnt to a temperature lower than 1000/sup 0/C -- melting point. Thus, the zeolite structure is broken to form fine amorphous silicate aluminate or silicate aluminate of the nuclide exchanged and adsorbed. Both are very hard to be soluble in water. Further, the lixiviation from the solidified body is limited to the surface thereof, and it will no longer be detected in a few days.

Radioactive effluents, Portsmouth Gaseous Diffusion Plant, calendar year 1982

International Nuclear Information System (INIS)

Acox, T.A.; Hary, L.F.; Klein, L.S.

1983-03-01

Radioactive discharges from the Portsmouth Gaseous Diffusion Plant are discussed and tabulated. Tables indicate both the location of the discharge and the nuclides discharged. All discharges for 1982 are well below the Radioactive Concentration Guide limits specified in DOE Order 5480.1, Chapter XI. 1 figure

Contribution of some food categories on intakes of U, Th and other nuclides

International Nuclear Information System (INIS)

Shiraishi, Kunio

1999-01-01

The assessment of radiation dose in human from radioactive 232 Th, 238 U, 137 Cs, and 90 Sr are important because those nuclides are the largest contributors to committed internal doses. A market basket study was conducted to clarify the food pathways of the nuclides in Japanese subjects. Foodstuffs of 336 were purchased from markets in the vicinity of Mito-City during 1994-1995. Statistical consumption data were used for collection of the food samples. Thorium-232, 238 U, and stable isotope ( 133 Cs) in eighteen food groups were determined by inductively coupled mass spectrometry (ICP-MS). Radioisotopes ( 137 Cs) was analyzed by γ-spectrometry. Stable strontium ( 88 Sr) was also analyzed by inductively coupled atomic emission spectrometry (ICP-AES). Big contributors to the nuclide intakes in Japanese were as follows: 232 Th fishes and shellfishes (44%) and green vegetables (11%); 238 U seaweeds (50%) and fishes and shellfishes (26%); 88 Sr seaweeds (53%) and fishes and shellfishes (14%); 137 Cs mushrooms (17%), fishes and shell fishes (15%), milk products (11%), meats (9%), and potatoes (7%). The food categories of oil and fats, eggs and cooked meals were minor contributors in those nuclides. Dietary intake studies by using eighteen or more food categories should be effective procedure to resolve critical food and critical pathway for Japanese. Furthermore, critical pathways of radionuclides could be estimated by the analyses of stable isotopes. (author)

Nuclear incineration method for long life radioactive wastes

International Nuclear Information System (INIS)

Matsumoto, Takaaki; Uematsu, Kunihiko.

1987-01-01

Nuclear incineration method is the method of converting the long life radioactive nuclides in wastes to short life or stable nuclides by utilizing the nuclear reaction caused by radiation, unlike usual chemical incineration. By the nuclear incineration, the radioactivity of wastes increases in a short period, but the problems at the time of the disposal are reduced because of the decrease of long life radioactive nuclides. As the radiation used for the nuclear incineration, the neutron beam from fission and fusion reactors and accelerators, the proton beam and gamma ray from accelerators have been studied. The object of the nuclear incineration is actinide, Sr-90, Cs-137, I-129 and Tc-99. In particular, waste actinide emits alpha ray, and is strongly toxic, accordingly, the motive of attempting the nuclear incineration is strong. In Japan, about 24t of waste actinide will accumulate by 2000. The principle of the nuclear incineration, and the nuclear incineration using nuclear fission and fusion reactors and accelerators are described. The nuclear incineration using fission reactors was examined for the first time in 1972 in USA. It is most promising because it is feasible by the present technology without particular research and development. (Kako, I.)

Chart of the nuclides

International Nuclear Information System (INIS)

Yoshizawa, Y.; Horiguchi, T.; Yamada, M.

1980-01-01

In this chart, four colors are use to classify nuclides according to their half-lives. The different symbols are also to show the decay modes and their percentage in each nuclide. Four tables are provided on the back of the chart. Table 1 is the ordinary periodic Table. Table 2 provides fundamental constants used for nuclear physics. Tables 3 lists the physical constants (mean density, ionization potential, melting point, and boiling point) of all elements. Table 4 provides the gamma-ray intensity standards. Half-lives, energy, relative intensity, and intensity per decay are list for 33 nuclides. (J.P.N.)

Distribution Of Natural Radioactivity On Soil Size Particles

International Nuclear Information System (INIS)

Tran Van Luyen; Trinh Hoai Vinh; Thai Khac Dinh

2008-01-01

This report presents a distribution of natural radioactivity on different soil size particles, taken from one soil profile. On the results shows a range from 52% to 66% of natural radioisotopes such as 238 U, 232 Th, 226 Ra and 40 K concentrated on the soil particles below 40 micrometers in diameter size. The remained of natural radioisotopes were distributed on a soil particles with higher diameter size. The study is available for soil sample collected to natural radioactive analyze by gamma and alpha spectrometer methods. (author)

International chart of the nuclides. 2001

International Nuclear Information System (INIS)

Golashvili, T.V.; Kupriyanov, V.M.; Lbov, A.A.

2002-01-01

The International Chart of Nuclides - 2001 has been developed taking into account the data obtained in 1998-2001. Unlike widespread nuclide charts the present Chart of Nuclides contains EVALUATED values of the main characteristics. These values are supplied with the standard deviations. (author)

Radio nuclides in mineral rocks and beach sand minerals in south east coast, Odisha

International Nuclear Information System (INIS)

Vidya Sagar, D.; Sahoo, S.K.; Essakki, Chinna; Tripathy, S.K.; Ravi, P.M.; Tripathi, R.M.; Mohanty, D.

2014-01-01

The primordial and metamorphic mineral rocks of the Eastern Ghats host minerals such as rutile, ilmenite, Silmenite, zircon, garnet and monazite in quartz matrix. The weathered material is transported down to the sea by run-off through Rivers and deposited back in coastal beach as heavy mineral concentrates. The minerals are mined by M/S Indian Rare Earths Ltd at the Chatrapur plant in Odisha coast to separate the individual minerals. Some of these minerals have low level radioactivity and may pose external and internal radiation hazard. The present paper deals with natural Thorium and Uranium in the source rocks with those observed in the coastal deposits. The study correlates the nuclide activity ratios in environmental samples in an attempt to understand the ecology of the natural radio nuclides of 238 U, 232 Th, 40 K and 226 Ra in environmental context. Further work is in progress to understand the geological process associated with the migration and reconcentration of natural radio-nuclides in the natural high background radiation areas

Study on fitness functions of genetic algorithm for dynamically correcting nuclide atmospheric diffusion model

International Nuclear Information System (INIS)

Ji Zhilong; Ma Yuanwei; Wang Dezhong

2014-01-01

Background: In radioactive nuclides atmospheric diffusion models, the empirical dispersion coefficients were deduced under certain experiment conditions, whose difference with nuclear accident conditions is a source of deviation. A better estimation of the radioactive nuclide's actual dispersion process could be done by correcting dispersion coefficients with observation data, and Genetic Algorithm (GA) is an appropriate method for this correction procedure. Purpose: This study is to analyze the fitness functions' influence on the correction procedure and the forecast ability of diffusion model. Methods: GA, coupled with Lagrange dispersion model, was used in a numerical simulation to compare 4 fitness functions' impact on the correction result. Results: In the numerical simulation, the fitness function with observation deviation taken into consideration stands out when significant deviation exists in the observed data. After performing the correction procedure on the Kincaid experiment data, a significant boost was observed in the diffusion model's forecast ability. Conclusion: As the result shows, in order to improve dispersion models' forecast ability using GA, observation data should be given different weight in the fitness function corresponding to their error. (authors)

A method for speciation of trace elements (stable and radioactive) in natural waters

International Nuclear Information System (INIS)

Salbu, B.; Bjornstad, H.E.; Pappas, A.C.

1985-01-01

Radioactive nuclides and stable trace metals entering natural aquatic systems interact with naturally occurring particles through exchange and sorption processes. The extent of which depends not only on the elements and particles in question, but also on size distribution of particles being most pronounced for colloids having large surface areas to volume ratios. The interaction of radionuclides and trace metals with colloids changes their size and charge characteristics and thereby influences their transport, mobility and bioavailability

Development of carrier usage for the treatment of radioactive effluent

Energy Technology Data Exchange (ETDEWEB)

Kahraman, A [Cekmece Nuclear Research and Training Center, Istanbul (Turkey)

1997-02-01

Low level radioactive liquid wastes are produced in many nuclear applications. Their physico-chemical characteristics may very considerably. Chemical precipitation is a convenient treatment method for the liquid streams of high salinity or solid content containing different radionuclide types. Generally, the concentrations of nuclides in liquid wastes are extremely low. For example, 1000 Bq of {sup 137}Cs makes about 3{center_dot}10{sup -10} g of caesium. Therefore conventional precipitation cannot be applied since the solubility product value is not exceeded. The carriers which are capable to adsorb the nuclides are used to achieve the nuclide removal. Stable isotopes of the nuclide are usually added as the carriers but any reagent which has similar chemical specifications with the nuclide can also be used as the carrier. Precipitation of these non-radioactive carriers ion together with the radionuclide is called co-precipitation. The operational steps of the chemical precipitation process should be established and applied in a treatment facility. Thus, the most suitable carrier for a particular nuclide and its usage conditions are required to be determined. In this study, the carriers for removal of {sup 137}Cs and uranium, their accurate amounts and usage conditions to achieve highest decontamination factors (DF) have been investigated. Residual sludge volumes were evaluated for cementation purposes. The cement composite samples were prepared for each set of experiments and hardening times were measured. 9 refs, 9 figs.

Study of the accumulation and distribution of the radioactivity in the cooling circuit of the BOR-60 reactor

International Nuclear Information System (INIS)

Kizin, V.D.; Konyashov, V.V.; Lisitsyn, E.S.; Polyakov, V.I.; Chechetkin, Yu.V.

1976-04-01

The results of measurements of the radioactivity of the coolant and the deposits in the primary circuit of the BOR-60 reactor during its five years of operation are discussed. The values calculated for the exposure dose rate from the piping system and the contribution of the γ-radiation from the corrosion and fission product nuclides are given. The efficiency of coolant draining from the pipes in reducing the dose rate is estimated. (orig.) [de

Decontamination Experiments on Intact Pig Skin Contaminated with Beta-Gamma- Emitting Nuclides

Energy Technology Data Exchange (ETDEWEB)

Edvardsson, K A; Hagsgaard, S [AB Atomenergi, Nykoeping (Sweden); Swensson, A [Dept. of Occupational Medicine, Karolinska Sjukhuset, Stockholm (Sweden)

1966-11-15

A number of decontamination experiments have been performed on intact pig skin. In most of the experiments NaI-131 in water solution has been utilized because this nuclide is widely used within the Studsvik research establishment, is easy to detect and relatively harmless, and is practical to use in these experiments. Among the {beta} {gamma}-nuclides studied 1-131 has furthermore proved to be the one most difficult to remove from the skin. The following conclusions and recommendations regarding the decontamination of skin are therefore valid primarily for iodine in the form of Nal, but are probably also applicable to many other {beta} {gamma}-nuclides. a) A prolonged interval between contamination and decontamination has a negative effect on the result of the decontamination. Therefore start decontamination as soon as possible after the contamination. b) Soap and water has proved to be the most suitable decontamination agent. A number of other agents have appeared to be harmful to the skin. Therefore, first of all use only soap and water in connection with gentle rubbing. c) No clear connection between the temperature of the water for washing and the result of the decontamination has been demonstrated. d) Skin not degreased before the contamination seems to be somewhat easier to decontaminate than degreased skin, particularly if the activity has been on the skin for a long time. Therefore do not remove the sebum of the skin when engaged on radioactive work involving contamination risks. e) Irrigation of the contaminated surface with a solution containing the corresponding inactive ions or ordinary water in large quantities may considerably decrease the skin contamination. f) In radioactive work of long duration involving high risks of contamination prophylactic measures in the form of a protective substance ('invisible glove'), type Kerodex, may make decontamination easier.

Decontamination Experiments on Intact Pig Skin Contaminated with Beta-Gamma- Emitting Nuclides

International Nuclear Information System (INIS)

Edvardsson, K.A.; Hagsgaard, S.; Swensson, A.

1966-11-01

A number of decontamination experiments have been performed on intact pig skin. In most of the experiments NaI-131 in water solution has been utilized because this nuclide is widely used within the Studsvik research establishment, is easy to detect and relatively harmless, and is practical to use in these experiments. Among the β γ-nuclides studied 1-131 has furthermore proved to be the one most difficult to remove from the skin. The following conclusions and recommendations regarding the decontamination of skin are therefore valid primarily for iodine in the form of Nal, but are probably also applicable to many other β γ-nuclides. a) A prolonged interval between contamination and decontamination has a negative effect on the result of the decontamination. Therefore start decontamination as soon as possible after the contamination. b) Soap and water has proved to be the most suitable decontamination agent. A number of other agents have appeared to be harmful to the skin. Therefore, first of all use only soap and water in connection with gentle rubbing. c) No clear connection between the temperature of the water for washing and the result of the decontamination has been demonstrated. d) Skin not degreased before the contamination seems to be somewhat easier to decontaminate than degreased skin, particularly if the activity has been on the skin for a long time. Therefore do not remove the sebum of the skin when engaged on radioactive work involving contamination risks. e) Irrigation of the contaminated surface with a solution containing the corresponding inactive ions or ordinary water in large quantities may considerably decrease the skin contamination. f) In radioactive work of long duration involving high risks of contamination prophylactic measures in the form of a protective substance ('invisible glove'), type Kerodex, may make decontamination easier

Nuclear power technology system with molten salt reactor for transuranium nuclides burning in closed fuel cycle

International Nuclear Information System (INIS)

Alekseev, P.N.; Dudnikov, A.A.; Ignatiev, V.V.; Prusakov, V.N.; Ponomarev-Stepnoy, N.N.; Subbotin, S.A.

2000-01-01

A concept of nuclear power technology system with homogeneous molten salt reactors for burning and transmutation of long-lived radioactive toxic nuclides is considered in the paper. Disposition of such reactors in enterprises of fuel cycle allows to provide them with power and facilitate solution of problems with rad waste with minimal losses. (Authors)

Evaluation of radon and radioactivity level in phosphorite area in Guizhou

International Nuclear Information System (INIS)

Li Zhou; Yang Zhong; Wei Tao; Zhang Xiaole; Yu Lixin; Tian Zhujuan

2006-01-01

Objective: To study and assess atmospheric radon and radioactive levels in one of phosphorite area in Guizhou province. Methods: To monitor and analyze the external irradiation level, atmospheric radon, nuclide levels, and water total radioactivity on the spot and in the laboratory. Results: External irradiation level is 7-18 x 10 -8 Gy/h, the mean value is 12 x 10 -8 Gy/h, atmospheric radon concentration is 105-246 Bq/m 3 , ore 226 Ra nuclide levels are between 156.7-372.3 Bq/kg, the mean value is 222.6 Bq/kg, the maximum total radioactivity levels of mine water are total α=0.175 Bq/L and total β=0.374 Bq/L, the total radioactivity levels of drinking water is not more than total α=0.0327 Bq/L, total β=0.174 Bq/L. Conclusion: Radioactivity levels accord with the relevant national standards. There were remarkable correlation in the total radioactivity levels of mine water and drinking water. The radon concentration in well air is not up to the point of reach intervention level. (authors)

Numeric determination and validation of neutron induced radioactive nuclide inventories for decommissioning and dismantling of light water reactors; Rechnerische Bestimmung und Validierung von Aktivierungsaktivitaeten fuer die Rueckbau- und Entsorgungsplanung von Leichtwasserreaktoren

Energy Technology Data Exchange (ETDEWEB)

Phlippen, Peter W.; Schloemer, Luc; Vallentin, Roger [WTI Wissenschaftlich-Technische Ingenieurberatung GmbH, Juelich (Germany); Lukas, Bernard [EnBW Kernkraft GmbH Kernkraftwerk Philippsburg (Germany); Palm, Stefan [EnBW Kernkraft GmbH Kernkraftwerk Neckarwestheim (Germany)

2017-02-15

The deconstruction of nuclear power plants requires project planning and budgeting both during the project and in advance, as well as the secured provision of financial and human resources. When a facility is free from irradiated fuel, the reactor pressure vessel with the nuclear components as well as the biological shield determine the activity inventory of the facility, which almost exclusively consists of activated radionuclides located in the respective structures. Knowledge of the activity distribution and nuclide vectors of the involved components is of vital importance for deconstruction planning. In this context, the development of a computation procedure is described coupling the Monte Carlo method for the determination of neutron flux densities with a procedure to perform activation calculations for the determination of nuclide vectors. For this purpose, detailed knowledge of the material composition, particularly the trace-element concentrations of nitrogen and cobalt in steel and additionally of europium and caesium in concrete structures, considerably impacts the accuracy of the calculated activities. Extensive validation using data collected from various reactor facilities, such as nuclide activities, neutron flux densities, and neutron and gamma dose rates, demonstrates the reliability of the computed nuclide distributions showing ratios of computed over measured values of typically between 0.9 and 3. The practicality of the developed method as well as the convenient use of the results have already been demonstrated analysing several German BWR and PWR facilities and developing packaging strategies based on the produced results.

Sampling soils for transuranic nuclides: a review

International Nuclear Information System (INIS)

Fowler, E.B.; Essington, E.H.

1976-01-01

A review of the literature pertinent to the sampling of soils for radionuclides is presented; emphasis is placed on transuranic nuclides. Sampling of soils is discussed relative to systems of heterogeneous distributions and varied particle sizes encountered in certain environments. Sampling methods that have been used for two different sources of contamination, global fallout, and accidental or operational releases, are included

High Accuracy mass Measurement of the very Short-Lived Halo Nuclide $^{11}$Li

CERN Multimedia

Le scornet, G

2002-01-01

The archetypal halo nuclide $^{11}$Li has now attracted a wealth of experimental and theoretical attention. The most outstanding property of this nuclide, its extended radius that makes it as big as $^{48}$Ca, is highly dependent on the binding energy of the two neutrons forming the halo. New generation experiments using radioactive beams with elastic proton scattering, knock-out and transfer reactions, together with $\\textit{ab initio}$ calculations require the tightening of the constraint on the binding energy. Good metrology also requires confirmation of the sole existing precision result to guard against a possible systematic deviation (or mistake). We propose a high accuracy mass determintation of $^{11}$Li, a particularly challenging task due to its very short half-life of 8.6 ms, but one perfectly suiting the MISTRAL spectrometer, now commissioned at ISOLDE. We request 15 shifts of beam time.

Basic study on behaviors of radioactive and toxic inorganic elements in environment, and environmental assessment for geological disposal of high-level radioactive wastes. Outline of the prize-winning study of the 12th Osaka Nuclear Science Corporation Prize

Energy Technology Data Exchange (ETDEWEB)

Fujikawa, Yoko; Kudo, Akira [Kyoto Univ., Kumatori, Osaka (Japan). Research Reactor Inst.

1999-01-01

This study was made aiming to establish geological disposal technology for high-level radioactive wastes generated in nuclear power plant. A basic study for the technology was made using various radioactive materials containing Pu, U, Cs, Se, etc. as a tracer. First, adsorption mechanisms of various nuclides in ground water such as Cs, Co, Se, etc. onto rocks were investigated by indoor experiment. A certain correlation between the apparent adsorption rate of a nuclide onto rocks and diffusion coefficient into micropores in rocks was demonstrated both theoretically and experimentally. To estimate the radionuclide migration during more than one thousand years based on the results from indoor experiments is difficult, so that construction of a mathematical model was attempted to make numerical simulation. Thus,it was suggested that the properties of underground barrier are considerably related to the adsorption rates of nuclides and also diffusion coefficients into micropores. In addition, the effects of soil microorganisms and organic compounds on the behaviors of radioactive nuclides in soil ecosphere were investigated by extra-low level analysis of long-life radioactivities. More than 10% of Pu derived from Atomic Bomb at Nagasaki were found to be strongly bound to organic compounds in soils, showing that the element is extremely reactive with organic substances. (M.N.)

A critical study on the IAEA definition of high level radioactive waste unsuitable for dumping at sea

International Nuclear Information System (INIS)

Miyake, Yasuo; Saruhashi, Katsuko.

1976-01-01

The definition of high level radioactive waste and other high level radioactive matter not suitable for dumping at sea has been given by IAEA (1975). Since this definition is based on the report by Webb and Morley (1973), a critical study is made on their report. The result of study shows that owing to the assumption of a very small value of the horizontal eddy diffusion coefficient (10 4 cm 2 /s) for the sake of safety for these nuclides, the limiting environmental capacity for such nuclides as 226 Ra and 239 Pu with longer half-lives is extremely overestimated. And due to a very small value of a daily intake of marine foods (6 g/d) and a larger value of the ratio of nuclidic concentrations between the top of the deep layer and the surface layer (100), the environmental capacity is also overestimated for every nuclide. It is proposed that the definition of high level radioactive waste should be reassessed carefully by experts in various countries. (auth.)

Radioactivity distribution measurement of various natural material surfaces with imaging plate

International Nuclear Information System (INIS)

Mori, C.; Suzuki, T.; Koido, S.; Uritani, A.; Yanagida, K.; Wu, Y.; Nishizawa, K.

1996-01-01

Distribution images of natural radioactivity in natural materials such as vegetables were obtained by using Imaging Platc. In ssuch cases, it is necessary to reduce background radiation intensity by one order or more. Graded shielding is very important. Espacially, the innermost surface of a shielding box sshould be covered with acrylic rein plate. We obtained natural radioactivity distribution images of vegetable, sea food, mea etc. Most β-rays emitted from 40 K print the radioactivity distribution image. Comparison between γ-ray intensity of KCL solution measured with HPGe detector and that of natural material specimen gave the radioactivity around 0.06- 0.04Bq/g depending on the kind and the part of specimens. (author). 6 refs., 5 figs., 1 tab

Device for the disposal of radioactive liquid wastes

International Nuclear Information System (INIS)

Tomizawa, Toshi; Inoue, Tadashi.

1976-01-01

Object: To adsorb and collect radioactive nuclide ions contained in the radioactive liquid waste to select and separate thereof. Structure: A unitary disposing tank comprises an insulative cylindrical tank, an unsoluble cathode plate positioned thereunder and formed with a number of liquid inlet holes, an adsorbent layer filled with unsoluble electrically conductive substances having a large surface area in contact with the cathode plate, and an unsoluble anode plate positioned at the upper part of the cylindrical disposing tank so as not to come into contact with the adsorbent layer and formed with a number of liquid inlets, whereby one or more disposing tanks are stacked in a layer fashion, and a DC voltage is applied between the anode and cathode plates to flow a liquid to be disposed into the disposing tanks so that the radioactive metal ion nuclide in the liquid may be adsorbed and collected by the cathode and the adsorbent layer for selection and separation. (Ohara, T.)

Evaluating future detriment from radioactive discharges

International Nuclear Information System (INIS)

Fleishman, A.B.; Clark, M.J.

1982-01-01

A quantitative framework for expressing judgements on the relative valuation of both future protection costs and radiation detriment from radioactive discharges is discussed. The framework can be applied to a series of notional effluent control options, illustrating the sensitivity of optimum protection levels to variations in discount rates. Using data on the radiological significance and management of radioactive discharges arising from the nuclear fuel cycle, it was shown that this quantitative optimization method of evaluating future detriment has important implications for the management of radioactive effluents, particularly those containing long-lived nuclides. (U.K.)

Pollution by radioactive iodine and radioactive cesium in fruit fields

International Nuclear Information System (INIS)

Ohtsuki, Tsutomu; Kikunaga, Hidetoshi; Izumi, Yuichi

2011-01-01

A lot of radioactive materials were spread out by the accident of the Fukushima Daiichi nuclear power station caused by the tsunami accompanying earthquake in the area of Tohoku district-Pacific Ocean, in 2011/3/11. In early stage, short half-life nuclides, such as "1"3"2Te, "1"3"1I, "1"3"6Cs, as well as "1"3"4Cs, "1"3"7Cs were observed in fields. Now "1"3"4Cs and "1"3"7Cs which are comparatively long half-life became dominant observing nuclides. The nuclear power plant accident brought serious damages in many directions, especially, the influence of the field pollution by these nuclides is great in the agriculture, and the quick actions and the measures are needed. The influence of "1"3"4Cs and "1"3"7Cs to the fruit tree were investigated in cooperation with Fukushima agricultural center, Institute of Fruit Tree Science. We report several facts of the transfer and translocation mechanism of "1"3"4Cs and "1"3"7Cs in fruit trees. (author)

Progress on multi-nuclide AMS of JAEA-AMS-TONO

Science.gov (United States)

Saito-Kokubu, Yoko; Matsubara, Akihiro; Miyake, Masayasu; Nishizawa, Akimitsu; Ohwaki, Yoshio; Nishio, Tomohiro; Sanada, Katsuki; Hanaki, Tatsumi

2015-10-01

The JAEA-AMS-TONO (Japan Atomic Energy Agency's Accelerator Mass Spectrometer established at the Tono Geoscience Center) facility has been used for the dating of geological samples. The AMS system is versatile, based on a 5 MV tandem Pelletron-type accelerator. Since its establishment in 1997, the AMS system has been used for measurement of carbon-14 (14C) mainly for 14C dating studies in neotectonics and hydrogeology, in support of JAEA's research on geosphere stability applicable to the long-term isolation of high-level radioactive waste. Results of the measurement of 14C in soils and plants has been applied to the dating of fault activity and volcanism. Development of beryllium-10 (10Be) and aluminum-26 (26Al) AMS systems are now underway to enhance the capability of the multi-nuclide AMS in studies of dating by cosmogenic nuclides. The 10Be-AMS system has already been used for routine measurements in applied studies and improvements of the measurement technique have been made. Now we plan to fine tune the system and perform test measurements to develop the 26Al-AMS system.

Progress on multi-nuclide AMS of JAEA-AMS-TONO

Energy Technology Data Exchange (ETDEWEB)

Saito-Kokubu, Yoko, E-mail: kokubu.yoko@jaea.go.jp [Japan Atomic Energy Agency, Toki, Gifu 509-5102 (Japan); Matsubara, Akihiro [Japan Atomic Energy Agency, Toki, Gifu 509-5102 (Japan); Miyake, Masayasu; Nishizawa, Akimitsu; Ohwaki, Yoshio; Nishio, Tomohiro; Sanada, Katsuki [Pesco Corp., Ltd., Toki, Gifu 509-5123 (Japan); Hanaki, Tatsumi [Japan Atomic Energy Agency, Toki, Gifu 509-5102 (Japan)

2015-10-15

The JAEA-AMS-TONO (Japan Atomic Energy Agency’s Accelerator Mass Spectrometer established at the Tono Geoscience Center) facility has been used for the dating of geological samples. The AMS system is versatile, based on a 5 MV tandem Pelletron-type accelerator. Since its establishment in 1997, the AMS system has been used for measurement of carbon-14 ({sup 14}C) mainly for {sup 14}C dating studies in neotectonics and hydrogeology, in support of JAEA’s research on geosphere stability applicable to the long-term isolation of high-level radioactive waste. Results of the measurement of {sup 14}C in soils and plants has been applied to the dating of fault activity and volcanism. Development of beryllium-10 ({sup 10}Be) and aluminum-26 ({sup 26}Al) AMS systems are now underway to enhance the capability of the multi-nuclide AMS in studies of dating by cosmogenic nuclides. The {sup 10}Be-AMS system has already been used for routine measurements in applied studies and improvements of the measurement technique have been made. Now we plan to fine tune the system and perform test measurements to develop the {sup 26}Al-AMS system.

Organ distribution of 137Cs in mouse fetuses and their dams

International Nuclear Information System (INIS)

Matsusaka, Naonori; Yamakawa, Yoji; Sato, Itaru; Tsuda, Shuji; Kobayashi, Haruo; Nishimura, Yoshikazu.

1997-01-01

A single dose of 137 Cs was given intravenously to pregnant mice on day 17 of gestation, and organ distribution of this nuclide in mouse fetuses and their dams was studied by measuring radioactivity and by macroautoradiography. Fetal uptake of 137 Cs was 0.8% of the initial dose 24 h after administration; about 11% of the initial dose was incorporated in litter during the same period. Concentrations of 137 Cs in fetal organs were 0.4-0.8%/g 24 h after administration, whereas concentrations in dams' organs were in a range of 2-6%/g. Therefore, concentrations in maternal organs such as liver, spleen, kidneys and muscle were 4-6 times higher than those in fetuses. Among the maternal organs, the salivary gland represented the highest concentration of 25%/g 1 h after administration to 6.4%/g 24 h after administration. This remarkable uptake in the salivary gland should be emphasized because of its close location to the thyroid gland in experimental animals and humans. Macroautoradiograms supported the findings obtained by measuring radioactivity in the organs. Macroautoradiograms in color may facilitate visual understanding of organ distribution of this nuclide. (author)

On barrier performance of high compaction bentonite in facilities of disposing high level radioactive wastes in formation

International Nuclear Information System (INIS)

Ikeda, Hidefumi; Komada, Hiroya

1989-01-01

As for the method of disposing high level radioactive wastes generated in the reprocessing of spent fuel, at present formation disposal is regarded as most promising. The most important point in this formation disposal is to prevent the leak of radioactive nuclides within the disposal facilities into bedrocks and their move to the zone of human life. As the method of formation disposal, the canisters containing high level radioactive wastes are placed in the horizontal or vertical holes for disposal dug from horizontal tunnels which are several hundreds m underground, and the tunnels and disposal holes are filled again. For this filling material, the barrier performance to prevent and retard the leak of radioactive nuclides out of the disposal facilities is expected, and the characteristics of low water permeability, the adsorption of nuclides and long term stability are required. However, due to the decay heat of wastes just after the disposal, high temperature and drying condition arises, and this must be taken in consideration. The characteristics required for filling materials and the selection of the materials, the features and classification of bentonite, the properties of high compaction bentonite, and the move of water, heat and nuclides in high compaction bentonite are reported.(Kako, I.)

Nuclide separation by hydrothermal treatment and ion exchange: a highly effective method for treatment of liquid effluents - 59217

International Nuclear Information System (INIS)

Braehler, Georg; Rieck, Ronald; Avramenko, V.A.; Sergienko, V.I.; Antonov, E.A.

2012-01-01

Liquid low level radioactive effluents, when solidified in e.g. cement matrix, contribute to a significant extent to the waste amount to be disposed of in final repositories. Accordingly, since many years scientists and engineers investigate processes to remove the radioactive nuclides selectively from the effluents, to split the raw solution into two separate fractions: a large fraction with activity concentrations below the limits for free release; and a small fraction, containing the activity in concentrated form on e. g. ion exchanger materials (ion exchange has proven to be the most promising method for such 'nuclide separation'). The challenge to be taken up is: When (and this is most often the case) the effluent contains organic materials and complexing agents, the formation of e. g. the 60-Co-EDTA complex prohibits its fixation to the ion exchangers. Accordingly the complexing agent needs to be removed or destroyed. The Institute for Chemistry of the Russian Academy of Sciences has applied the method of hydrothermal treatment (at elevated temperature and pressure, 200 deg. C, 200 bar), supported by Hydrogen Peroxide oxidation, to allow virtually complete removal of radioactive nuclides on inorganic ion exchangers. Pilot plants have been operated successfully in Russian power stations, and an operational plant has been designed. The method is being extended for an interesting and promising application: spent organic ion exchange resins, loaded up to the medium activity level, represent a serious disposal problem. With the hydrothermal process, in a process cycle, the activity can be stripped from the resins, the organic content is destroyed, and the activity is fixed on an inorganic absorber, well suited for final disposal. (authors)

Trapping radioactive ions

CERN Document Server

Kluge, Heinz-Jürgen

2004-01-01

Trapping devices for atomic and nuclear physics experiments with radioactive ions are becoming more and more important at accelerator facilities. While about ten years ago only one online Penning trap experiment existed, namely ISOLTRAP at ISOLDE/CERN, meanwhile almost every radioactive beam facility has installed or plans an ion trap setup. This article gives an overview on ion traps in the operation, construction or planing phase which will be used for fundamental studies with short-lived radioactive nuclides such as mass spectrometry, laser spectroscopy and nuclear decay spectroscopy. In addition, this article summarizes the use of gas cells and radiofrequency quadrupole (Paul) traps at different facilities as a versatile tool for ion beam manipulation like retardation, cooling, bunching, and cleaning.

Trapping radioactive ions

International Nuclear Information System (INIS)

Kluge, H.-J.; Blaum, K.

2004-01-01

Trapping devices for atomic and nuclear physics experiments with radioactive ions are becoming more and more important at accelerator facilities. While about ten years ago only one online Penning trap experiment existed, namely ISOLTRAP at ISOLDE/CERN, meanwhile almost every radioactive beam facility has installed or plans an ion trap setup. This article gives an overview on ion traps in the operation, construction or planing phase which will be used for fundamental studies with short-lived radioactive nuclides such as mass spectrometry, laser spectroscopy and nuclear decay spectroscopy. In addition, this article summarizes the use of gas cells and radiofrequency quadrupole (Paul) traps at different facilities as a versatile tool for ion beam manipulation like retardation, cooling, bunching, and cleaning

Proceedings of the International conference on radioecology and environmental radioactivity

International Nuclear Information System (INIS)

2008-01-01

The conference contains 404 presentations on: 1) Emergency preparedness and rehabilitation with emphasis on radiation and radioactivity determination and monitoring, protection and contamination and pollution. 2) TNORM/NORM including radon with focus on radioactivity in the environmental and isotope evaluation. 3) Radioecology and speciation including arctic radioecology, focusing on accidents, radiation and radioactivity effects, nuclear waste disposal, handling, impacts, safety and risks, pollution and its sources, accumulation of isotopes and various medical aspects. 4) Risk assessment with emphasis on the environmental and ecological aspects, modeling, recommendations and international cooperation and discussion of the effects of climatic changes. 5) Radiation in society. 6) Environmental protection with focus on radionuclide studies, radiation effects and protection measures, isotope accumulation effects, nuclide distribution, migration and pollution and effects and handling of nuclear accidents. The global aspects of the topics are evident and there are discussions on non-ionizing and ionizing radiation effect, various simulation problems and public and general health aspects (tk)

Library correlation nuclide identification algorithm

International Nuclear Information System (INIS)

Russ, William R.

2007-01-01

A novel nuclide identification algorithm, Library Correlation Nuclide Identification (LibCorNID), is proposed. In addition to the spectrum, LibCorNID requires the standard energy, peak shape and peak efficiency calibrations. Input parameters include tolerances for some expected variations in the calibrations, a minimum relative nuclide peak area threshold, and a correlation threshold. Initially, the measured peak spectrum is obtained as the residual after baseline estimation via peak erosion, removing the continuum. Library nuclides are filtered by examining the possible nuclide peak areas in terms of the measured peak spectrum and applying the specified relative area threshold. Remaining candidates are used to create a set of theoretical peak spectra based on the calibrations and library entries. These candidate spectra are then simultaneously fit to the measured peak spectrum while also optimizing the calibrations within the bounds of the specified tolerances. Each candidate with optimized area still exceeding the area threshold undergoes a correlation test. The normalized Pearson's correlation value is calculated as a comparison of the optimized nuclide peak spectrum to the measured peak spectrum with the other optimized peak spectra subtracted. Those candidates with correlation values that exceed the specified threshold are identified and their optimized activities are output. An evaluation of LibCorNID was conducted to verify identification performance in terms of detection probability and false alarm rate. LibCorNID has been shown to perform well compared to standard peak-based analyses

Yields and spectroscopy of radioactive isotopes at LOHENGRIN and ISOLDE

CERN Document Server

Köster, U

1999-01-01

Yields of radioactive nuclei were measured at two facilities: the recoil separator LOHENGRIN at the Institut Laue Langevin in Grenoble and the on-line isotope separator ISOLDE at CERN in Geneva. At LOHENGRIN the yields of light charged particles were measured from thermal neutron induced ternary fission of several actinide targets: 233U, 235U, 239Pu, 241Pu and 245Cm. Thin targets are brought into a high neutron flux. The produced nuclei leave these with the recoil obtained in the fission reaction. They are measured at different energies and ionic charge states. After corrections for the experimental acceptance, the time behaviour of the fission rate and the ionic charge fraction, the yields are integrated over the kinetic energy distribution. Comparing these yields with the predictions of various ternary fission models shows that the most abundant nuclides are well reproduced. On the other hand the models overestimate significantly the production of more "exotic" nuclides with an extreme N/Z ratio. Therefore ...

Disposal of radioactive waste material to sea

International Nuclear Information System (INIS)

Burton, W.R.

1985-01-01

Radioactive waste liquid of a low or intermediate activity level is mixed with a suitable particulate material and discharged under the sea from a pipeline. The particulate material is chosen so that it sorbs radio-nuclides from this waste, has a good retention for these nuclides when immersed in sea water, and has a particle size or density such that transfer of the particles back to the shore by naturally occurring phenomena is reduced. Radio nuclide concentration in the sea water at the end of the pipeline may also be reduced. The particulate material used may be preformed or co-precipitated in the waste. Suitable materials are oxides or hydroxides of iron or manganese or material obtained from the sea-bed. (author)

Development of solid water-equivalent radioactive certified reference materials

International Nuclear Information System (INIS)

Finke, E.; Greupner, H.; Groche, K.; Rittwag, R.; Geske, G.

1991-01-01

This paper presents a brief description of the development of solid water-equivalent beta volume radioactive certified reference materials. These certified reference materials were prepared for the beta fission nuclides 90 Sr/ 90 Y, 137 Cs, 147 Pm and 204 Tl. Comparative measurements of liquid and solid water-equivalent beta volume radioactive certified reference materials are discussed. (author)

NON-CONVENTIONAL PET NUCLIDES: PRODUCTION AND IMAGING

OpenAIRE

Laforest, Richard

2015-01-01

Abstract Medical cyclotrons are now commonly used for the production of PET nuclides by the (pn) reaction. These devices are typically capable of delivering 10-15 MeV protons beams at sufficiently high intensity for timely production of β+ decaying nuclides. Non-conventional PET nuclides have emerged recently and offers new opportunities for diagnostic and therapy drug discovery. In this paper, we will review the production capabilities for such nuclides at Washington University Medical Schoo...

Origin and Distribution of 26Al and Mg Isotopes in the Solar Protoplanetary Disk

DEFF Research Database (Denmark)

Larsen, Kirsten Kolbjørn

of short-lived radioactive nuclides in these ancient materials is a direct reflection of their recent nucleosynthetic origin prior to or during formation of our young solar system 4.6 Myr ago. Disentangling the origin and distribution of this nucleosynthetic heritage provides a fossil record of the dynamic......Understanding when and how our solar system formed is perhaps one of the most fundamental questions in natural sciences. The prime cosmochemical tools to achieve this goal are the remnants of the earliest stages of planet formation; meteorites and their components. Evidence for the former presence...... birth environment of our Sun and a unique time-window into the very earliest history of our solar system. Ever since the discovery of its decay product, 26Mg, in primitive solar system objects more than 30 years ago, the short-lived radioactive nuclide, 26Al (t1/2 = 0.73 Myr), has been the optimal...

Decommissioning Strategies Selection for Facilities Using Radioactive Material

International Nuclear Information System (INIS)

Husen Zamroni; Jaka Rachmadetin

2008-01-01

The facilities using radioactive material that have been stopped operation will require some form of the decommissioning for public and environment safety. The approaches are identified by three decommissioning strategies: immediate dismantling, deferred dismantling and entombment. If a facility undergoes immediate dismantling, most radio nuclides will have no such sufficient time to decay and therefore this strategy may not provide reduction in the worker exposure. A facility that undergoes deferred dismantling may advantage from the radioactive decay of residual radio nuclides during the long term storage period and entombment could be a viable option for other nuclear facilities containing only short lived or limited concentrations of long lived radionuclides. Mostly, only two types of the decommissioning used to be done in the world, immediate and deferred dismantling. (author)

Doses from radioactive methane

International Nuclear Information System (INIS)

Phipps, A.W.; Kendall, G.M.; Fell, T.P.; Harrison, J.D.

1990-01-01

A possible radiation hazard arises from exposure to methane labelled with either a 3 H or a 14 C nuclide. This radioactive methane could be released from a variety of sources, e.g. land burial sites containing radioactive waste. Standard assumptions adopted for vapours would not apply to an inert alkane like methane. This paper discusses mechanisms by which radioactive methane would irradiate tissues and provides estimates of doses. Data on skin thickness and metabolism of methane are discussed with reference to these mechanisms. It is found that doses are dominated by dose from the small fraction of methane which is inhaled and metabolised. This component of dose has been calculated under rather conservative assumptions. (author)

Leaching of radioactive nuclides from cement grouts. Part II

International Nuclear Information System (INIS)

Stanley, W.T.; Avgerinos, G.F.; Gonzalez, B.; Hemley, P.J.

1974-01-01

The determination of the leaching rate of radioactive 137 Cs from a cement grout should the grout be contacted by water is necessary for environmental protection. The effect of the leachant turnover rate on 137 Cs leaching rates was evaluated with batch and continuous (modified Soxhlet extractor) modes of experimentation. Three additives (Grundite, potter's clay, and Conasauga shale) were compared in terms of capability of radioactive isotope retention, while two leachants (tap and distilled water) were investigated. The Soxhlet extractor experiment resulted in the highest rate of leaching, and Conasauga shale was found the best additive for 137 Cs immobilization. Tap water used as leachant was more effective than distilled water. Data were analyzed using models involving isotopic diffusion in the grout and involving diffusion plus a time dependent boundary condition at the interface of grout specimen and leachant

Development of ACBIO: A Biosphere Template Using AMBER for a Potential Radioactive Waste Repository

International Nuclear Information System (INIS)

Lee, Youn Myoung; Hwang, Yong Soo; Kang, Chul Hyung; Hahn, Pil Soo

2005-01-01

Nuclides in radioactive wastes are assumed to be transported in the geosphere by groundwater and probably discharged into the biosphere. Quantitative evaluation of doses to human beings due to nuclide transport in the geosphere and through the various pathways in the biosphere is the final step of safety assessment of the radioactive waste repository. To calculate the flux to dose conversion factors (DCFs) for nuclides appearing at GBIs with their decay chains, a template ACBIO which is an AMBER case file based on mathematical model for the mass transfer coefficients between the compartments has been developed considering material balance among the compartments in biosphere and then implementing to AMBER, a general and flexible software tool that allows to build dynamic compartment models. An illustrative calculation with ACBIO is shown.

ZZ REAC-2, Nuclide Activation and Transmutation

International Nuclear Information System (INIS)

Mann, F.M.

2002-01-01

abundances, decay rates, dose rates, heating rates, etc. in a user-specified file format. SLIB converts one or more card-image format libraries into binary form for program use. Two auxiliary codes, LISTCRS and LISTDCY, are included to edit the cross section and decay binary data files, respectively. 2 - Method of solution: The spectrum-averaged cross section is obtained by collapsing the multigroup cross sections with the multigroup flux. The equations used assume that the cross sections are for a point in space and ignore the spatial transport of material and the time dependence of the cross sections. In order to provide a fast, stable solution to the transmutation equation, REAC2 lessens the couplings between nuclides implied by the transmutation equation. The code assumes that during any time period of arbitrary length (1) the flux is constant as a function of time, (2) no reaction occurs on a reaction product or a decay product, and (3) at most six decays can occur for a reaction product or the initial nuclide. Using these assumptions, REAC2 calculates exactly the resulting distribution of nuclides. Once the distribution is known, other quantities of interest such as the decay rate, dose rate, transmutations, etc. can be calculated from a linear combination of the nuclide amounts. 3 - Restrictions on the complexity of the problem: REAC2 is not optimized for problems where fission products are important

Parameters for several plutonium nuclides and 252Cf of safeguards interest

International Nuclear Information System (INIS)

Zucker, M.S.; Holden, N.E.

1984-01-01

Sets of the neutron emission multiplicity distribution gleaned from the literature for plutonium nuclides and 252 Cf are considered. A methodology for rendering the different sets comparable is presented and used to convert the sets to a common basis such that the differences can be evaluated objectively and that allows realistic estimate of the uncertainties. This in turn permits development of a canonical consensus set in certain instances. Evaluated data on the average neutron multiplicity, the total half-lives, and the half-lives for spontaneous fission are also given. A careful search of the literature reveals that the data on neutron multiplicity distributions for many nuclides is surprisingly sparse, considering that almost thirty years has elapsed since the original pioneering work, which in some cases, yield the only reported value. 93 references, 26 tables

An introduction to in-situ produced cosmogenic nuclides

International Nuclear Information System (INIS)

Norton, K.P.

2012-01-01

Cosmogenic nuclides are produced through interactions between cosmic rays and target nuclei in Earth's atmosphere and surface materials. Those which are produced in Earth's atmosphere are termed 'meteoric' while the nuclides produced in surface material are known as in-situ cosmogenic nuclides. The past two decades have seen a proliferation of applications for cosmogenic nuclides. This is primarily due to a revolution in accelerator mass spectrometry, AMS, measurement techniques which has allowed the measurement of very small amounts of nuclides. The following is a brief introduction to the theory and application of in-situ produced cosmogenic nuclide methods. (author). 17 refs., figs., 1 tab.

Calculation of radioactive inventory of activated parts for nuclear power unit and analysis of influence factors

International Nuclear Information System (INIS)

Liu Yang; Cai Qi; Lin Xiaoling

2011-01-01

Based on the operation characteristics of the nuclear power unit, the radioactive inventory of activated parts was calculated by ORIGEN2, and the effects of bum-up, operation mode and power change on the radioactive inventory for activated parts were analyzed. The results indicated that the radioactive inventory grew with the increasing of burn-up, and when the actual operation time was longer than the effective operation time, the increasing rate of nuclide activity approximated the burn-up increasing; Radioactive inventory of activated parts was influenced directly by the operation modes of the nuclear power unit, and under same reactor load, operation power and bum-up, the radioactive inventory for non-continuous operation mode is less than that for the continuous operation mode. Effects of operation modes on radioactive inventory reversed with half life of nuclides. Under same bum-up and longer operation time, the effect of operation power change on the radioactive inventory is not obvious, (authors)

Nuclide Inventory Calculation Using MCNPX for Wolsung Unit 1 Reactor Decommissioning

Energy Technology Data Exchange (ETDEWEB)

Rabir, Mohamad Hairie; Noh, Kyoung Ho; Hah, Chang Joo [KEPCO International Nuclear Graduate School, Daejeon (Korea, Republic of)

2014-05-15

The CINDER90 computation process involves utilizing linear Markovian chains to determine the time dependent nuclide densities. The CINDER90 depletion algorithm is implemented the MCNPX code package. The coupled depletion process involves a Monte-Carlo steady-state reaction rate calculation linked to a deterministic depletion calculation. The process is shown in Fig.1. MCNPX runs a steady state calculation to determine the system eigenvalue collision densities, recoverable energies from fission and neutrons per fission events. In order to generate number densities for the next time step, the CINDER90 code takes the MCNPX generated values and performs a depletion calculation. MCNPX then takes the new number densities and caries out a new steady-stated calculation. The process repeats itself until the final time step. This paper describe the preliminary source term and nuclide inventory calculation of Candu single fuel channel using MCNPX, as a part of the activities to support the equilibrium core model development and decommissioning evaluation process of a Candu reactor. The aim of this study was to apply the MCNPX code for source term and nuclide inventory calculation of Candu single fuel channel. Nuclide inventories as a function of burnup will be used to model an equilibrium core for Candu reactor. The core lifetime neutron fluence obtained from the model is used to estimate radioactivity at the stage of decommisioning. In general, as expected, the actinides and fission products build up increase with increasing burnup. Despite the fact that the MCNPX code is still in development we can conclude that the code is capable of obtaining relevant results in burnup and source term calculation. It is recommended that in the future work, the calculation has to be verified on the basis of experimental data or comparison with other codes.

Inventories of radioactive fission products in the core of thermal nuclear reactor

International Nuclear Information System (INIS)

Marinkovic, N.

1977-01-01

As a part of the analysis concerning radiological consequences of a major LWR accident, inventories of the most significant radioactive nuclides and stable fission gases in the core of a PWR type reactor have been calculated. Calculations were performed by the DELFIN code using nuclide data and neutron flux data earlier obtained by the METHUSELAH code. Comparison with simplified calculation method show that it is quite rough for certain nuclides but the accuracy may be sufficient for safety analysis purposes recalling the inaccuracies in the later parts of fission product transport process (author)

Development and application of the generator for the short-living nuclides production

International Nuclear Information System (INIS)

Tsejner, A.

1979-01-01

The results are stated of investigations by means of radioisotopes on the substance transfer in technological equipment. For these purposes, in most cases, nuclides with high gamma-activity are used and, if possible, having short half-life because the short half-life gives certain advantages in the cases when it is impossible to store radioactive substances in the technological equipment for a long time. It is noted that in connection with short half-life of the nucludes used for labelling and for the economic and radiation safety reasons, activity of these nuclides can not be high. It has been established that the most suitable nuclide for the labelling purpose is lanthanum-140 produced either in a nuclear reactor, or by means of separation from barium=-140 transforming into lanthanum-140 in an isotopic generator. Some methods of lanthanum separation from barium are described, in particular, in the isotopic generator described, barium is adsorbed on the cation-exchanger KPS-200 having high enough stability with respect to the ionozing radiations. As an eluent the 10 -2 M solution of the complexone (Na 2 - EDTA) was used. The complexone solution can be easely obtained and, because of the hydrolysis, it serves as a buffer solution. The data are given for radiation purity and yield of lanthanum-=140 [ru

Sampling of soils for transuranic nuclides: a review

International Nuclear Information System (INIS)

Fowler, E.B.; Essington, E.H.

1977-01-01

A review of the literature pertinent to the sampling of soils for radionuclides is presented; emphasis is placed on transuranic nuclides. Sampling of soils is discussed relative to systems of heterogeneous distributions and varied particle sizes encountered in certain environments. Sampling methods that have been used for two different sources of contamination, global fallout, and accidental or operational releases, are included

Development of solid water-equivalent radioactive certified reference materials

Energy Technology Data Exchange (ETDEWEB)

Finke, E.; Greupner, H.; Groche, K.; Rittwag, R. (Office for Standardization, Metrology and Quality Control (ASMW), Berlin (Germany, F.R.)); Geske, G. (Jena Univ. (Germany, F.R.))

1991-01-01

This paper presents a brief description of the development of solid water-equivalent beta volume radioactive certified reference materials. These certified reference materials were prepared for the beta fission nuclides {sup 90}Sr/{sup 90}Y, {sup 137}Cs, {sup 147}Pm and {sup 204}Tl. Comparative measurements of liquid and solid water-equivalent beta volume radioactive certified reference materials are discussed. (author).

Radioactive wastes in nuclear fuel cycle

International Nuclear Information System (INIS)

Sakata, Sadahiro; Nagaike, Tadakatsu; Emura, Satoru; Matsumoto, Akira; Morisawa, Shinsuke.

1978-01-01

Recent topics concerning radioactive water management and disposal are widely reviewed. As the introduction, various sources of radioactivity including uranium mining, fuel fabrication, reactor operation and fuel reprocessing and their amount of wastes accumulated per 1000 MWe year operation of a LWR are presented together with the typical methods of disposal. The second section discusses the problems associated with uranium fuel fabrication and with nuclear power plants. Typical radioactive nuclides and their sources in PWRs and BWRs are discussed. The third section deals with the problems associated with reprocessing facilities and with mixed oxide fuel fabrication. Solidification of high-level wastes and the methods of the disposal of transuranic nuclides are the main topics in this section. The fourth section discusses the methods and the problems of final disposal. Various methods being proposed or studied for the final disposal of low- and high-level wastes and transuranic wastes are reviewed. The fifth section concerns with the risk analysis of waste disposal. Both deterministic and probabilistic methods are treated. As the example, the assessment of the risk due to floods is explained. The associated event tree and fault three are presented together with the estimated probability of the occurrence of each constituent failure. In the final section, the environmental problems of radioactive wastes are widely reviewed. (Aoki, K.)

Disposal method of radioactive wastes

International Nuclear Information System (INIS)

Uetake, Naoto; Fukazawa, Tetsuo.

1986-01-01

Purpose: To improve the safety of underground disposal of radioactive wastes for a long period of time by surrounding the periphery of the radioactive wastes with materials that can inhibit the migration of radioactive nuclides and are physically and chemically stable. Method: Hardening products prepared from a water-hardenable calcium silicate compound and an aqueous solution of alkali silicate have compression strength as comparable with that of concretes, high water tightness and adsorbing property to radioactive isotopes such as cobalt similar to that of concretes and they also show adsorption to cesium which is not adsorbed to concretes. Further, the kneaded slurry thereof is excellent in the workability and can be poured even into narrow gaps. Accordingly, by alternately charging granular radioactive wastes and this slurry before hardening into the ground, the radioactive wastes can be put to underground disposal stably with simple procedures. (Kamimura, M.)

Transfer of nuclides from the water phase to the sediments during normal and extraordinary hydrological cycles

International Nuclear Information System (INIS)

1985-07-01

Atucha I and Atucha II nuclear power plants are located on the right margin of the Parana de las Palmas river. This river belongs to the Cuenca del Plata, whose 1982-1983 hydrologic cycle registered the greatest freshets of the century. Works and studies previously fixed had to be altered and investigations were adapted to the possibilities and the particular hydric conditions verified. Considerations on the transfer of nuclides between water and sediments are presented. The floods reduce the water-sediments contact time on the bed of the river. In outer areas, the waters labelled by the nuclear power plant effluent discharge favor the infiltration in alluvial soils, as well as the exchange with the sediments. The investigations carried out for the phase near to the discharge of liquid effluents (related to the critical group) made possible to prove the characteristics of the path of the liquid wastes released, the distribution coefficient and the fixation or penetrability of some nuclides in soils of the floody valley. In this manner, a balance of radioactive nuclides incorporated to soils and sediments from the neighbourhood of Atucha and the water-course of Parana de las Palmas river is obtained. The presence of 60 Co and 137 Cs in the floody soils on the right margin of this river was detected and measured during the greatest flood of the century. On the other hand, 144 Ce, 51 Cr, 106 Ru and 90 Sr have not been detected. The detection of artificial radioisotopes turns out to be impossible in normal hydrological years, even in the sorroundings of the nuclear power plant or the critical group (from the point of view of the surface waters, The Fishing Club, 3 km down stream). (M.E.L.) [es

Distribution of radioactive minerals in a granite

Energy Technology Data Exchange (ETDEWEB)

Coppens, R

1949-04-04

The study, by means of a photographic plate, of the radioactivity of a Brittany granite, both of a pulverized sample and of a polished sample, has resulted in a complete determination of the radioactivity present. The ratio of the concentration of Th to that of U i.e., C/sub Th/C/sub U/, was determined as approximately 2.8 using the relationship between the concentration of these elements and the number of ..beta.. particles in a particular range which were detected. Using this ratio and measuring the average number of ..cap alpha.. particles emitted/cm/sup 2//sec, the average activities were found to correspond to concentrations of the order of 10/sup -5/ of both metals. The lack of uniformity in the distribution of the radioactivity within the crystal is noted.

Decay and Transmutation of Nuclides

CERN Document Server

Aarnio, Pertti A

1999-01-01

We present a computer code DeTra which solves analytically the Bateman equations governing the decay, build-up and transmutation of radionuclides. The complexity of the chains and the number of nuclides are not limited. The nuclide production terms considered include transmutation of the nuclides inside the chain, external production, and fission. Time dependent calculations are possible since all the production terms can be re-defined for each irradiation step. The number of irradiation steps and output times is unlimited. DeTra is thus able to solve any decay and transmutation problem as long as the nuclear data i.e. decay data and production rates, or cross sections, are known.

A compartment model for nuclide release calculation in the near-and far-field of a HLW repository

International Nuclear Information System (INIS)

Lee, Youn Myoung; Hwang, Yong Soo; Kang, Chul Hyung; Hahn, Pil Soo

2004-01-01

The HLW-relevant R and D program for disposal of high-level radioactive waste has been carried out at Korea Atomic Energy Research Institute (KAERI) since early 1997, from which a conceptual Korea Reference Repository System for direct disposal of nuclear spent fuel is to be introduced by the end of 2007. A preliminary reference geologic repository concept considering such established criteria and requirements as spent fuel and generic site characteristics in Korea was roughly envisaged in 2003. Not only to demonstrate how much a reference repository is safe in the generic point of view with several possible scenarios and cases associated with a preliminary repository concept by conducting calculations for nuclide release and transport in the near - and far - field components of the repository, even though sufficient information has not been available that much yet, but also to show a appropriate methodology by which both a generic and site - specific safety assessment could be performed for further in - depth development of Korea reference repository concept, nuclide release calculation study for various nuclide release cases is mandatory. To this end a similar study done and yet limited for the near - field release case has been extended to the case including far - field system by introducing some more geosphere compartments. Advective and longitudinal dispersive nuclide transports along the fracture with matrix diffusion as well as several retention mechanisms and nuclide ingrowth has been added

Production of radioactive nuclides in inverse reaction kinematics

International Nuclear Information System (INIS)

Traykov, E.; Rogachevskiy, A.; Bosswell, M.; Dammalapati, U.; Dendooven, P.; Dermois, O.C.; Jungmann, K.; Onderwater, C.J.G.; Sohani, M.; Willmann, L.; Wilschut, H.W.; Young, A.R.

2007-01-01

Efficient production of short-lived radioactive isotopes in inverse reaction kinematics is an important technique for various applications. It is particularly relevant when the isotope of interest is only a few nucleons away from a stable isotope. In this article production via charge exchange and stripping reactions in combination with a magnetic separator is explored. The relation between the separator transmission efficiency, the production yield, and the choice of beam energy is discussed. The results of some exploratory experiments will be presented

Estimation of radioactive effluents dispersion from the nuclear power plants in Yugoslavia surrounding

International Nuclear Information System (INIS)

Vehauc, A.

1997-01-01

The computational method for atmospheric dispersion of radioactive effluents is applied to the nuclear power plants in Yugoslavia surrounding. On the basis of computation results, ground level concentrations and washout of radioactive nuclides on exposed Yugoslav territories during unfavourable meteorological conditions are estimated. (author)

Light nuclides produced in the proton-induced spallation of {sup 238}U at 1 GeV

Energy Technology Data Exchange (ETDEWEB)

Ricciardi, M.V.; Armbruster, P. [Gesellschaft fuer Schwerionenforschung mbH, Darmstadt (Germany); Benlliure, J. [Universidad de Santiago de Compostela (ES)] [and others

2005-09-01

The production of light and intermediate-mass nuclides formed in the reaction {sup 1}H+{sup 238}U at 1 GeV was measured at the fragment separator (FRS) at GSI, Darmstadt. The experiment was performed in inverse kinematics, shooting a 1 A GeV {sup 238}U beam on a thin liquid-hydrogen target. 254 isotopes of all elements in the range 7{<=}Z{<=}37 were unambiguously identified, and the velocity distributions of the produced nuclides were determined with high precision. The results show that the nuclides are produced in a very asymmetric binary decay of heavy nuclei originating from the spallation of uranium. All the features of the produced nuclides merge with the characteristics of the fission products as their mass increases. (orig.)

User manual of nuclide dispersion in phreatic aquifers model

International Nuclear Information System (INIS)

Rives, D.E.

1999-01-01

The Nuclide Dispersion in Phreatic Aquifers (DRAF) model was developed in the 'Division Estudios Ambientales' of the 'Gerencia de Seguridad Radiologica y Nuclear, Comision Nacional de Energia Atomica' (1991), for the Safety Assessment of Near Surface Radioactive Waste Disposal Facilities. Afterwards, it was modified in several opportunities, adapting it to a number of application conditions. The 'Manual del usuario del codigo DRAF' here presented is a reference document for the use of the last three versions of the code developed for the 'Autoridad Regulatoria Nuclear' between 1995 and 1996. The DRAF model solves the three dimension's solute transport equation for porous media by the finite differences method. It takes into account the advection, dispersion, radioactive decay, and retention in the solid matrix processes, and has multiple possibilities for the source term. There are three versions of the model, two of them for the saturated zone and one for the unsaturated zone. All the versions have been verified in different conditions, and have been applied in exercises of the International Atomic Energy Agency and also in real cases. (author)

Radioactivity and foods

International Nuclear Information System (INIS)

Olszyna-Marzys, A.E.

1991-01-01

The purpose of this article is to describe and contrast two relationships between radiation and food on the one hand, beneficial preservation of food by controlled exposure to ionizing radiation; and, on the other, contamination of food by accidental incorporation of radioactive nuclides within the food itself. In food irradiation, electrons or electromagnetic radiation is used to destroy microorganisms and insects or prevent seed germination. The economic advantages and health benefits of sterilizing food in this manner are clear, and numerous studies have confirmed that under strictly controlled conditions no undesirable changes or induced radioactivity is produced in the irradiated food. An altogether different situation is presented by exposure of food animals and farming areas to radioactive materials, as occurred after the major Soviet nuclear reactor accident at Chernobyl. This article furnishes the basic information needed to understand the nature of food contamination associated with that event and describes the work of international organizations seeking to establish appropriate safe limits for levels of radioactivity in foods

Germanium detector calibration according to the standard NF M 60-810 without using radioactive sources

Energy Technology Data Exchange (ETDEWEB)

Duda, J. M.; Garell, I.; Losset, Y.; Vichot, L. [CEA de Valduc, Service de Protection Contre Les Rayonnements, 21110 Is sur Tille (France); Chazalet, J.; Tauvel, Y.; Poulet, F. [IUP Genie des Systemes Industriels, Universite Blaise Pascal, Departement de Physique, 24 avenue des Landais, 63177 Aubiere Cedex (France)

2009-07-01

In-situ gamma ray spectrometry is used to determine the specific activities of natural and artificial radioactive nuclides in the soil with a good accuracy. This method is very interesting for environmental measurements and leads to soil determination activity. It is a cheaper method than analysis of great amounts of soil samples in the laboratory. As there is no standard soil, detection efficiency can be estimated using either statistical tools or combination of radioactive point sources calibration thanks to mathematical models of NF-M-60-810 standard representing the radionuclide distribution in soil. Experimental determination of detection efficiency requires a large number of operations involving the handling of radioactive standards in the energy range from 0.06 - 2 MeV. For these reasons, detection efficiency model has been determined without using radioactive sources. In order to reduce analytical time and to simplify the efficiency detector calibration, it is possible to associate numerical and deterministic methods and to get a relative accuracy below 25 per cent

Mass measurement of radioactive isotopes

CERN Document Server

Kluge, H J; Scheidenberger, C

2004-01-01

The highest precision in mass measurements on short-lived radionuclides is obtained using trapping and cooling techniques. Here, the experimental storage ring (ESR) at GSI/Darmstadt and the tandem Penning trap mass spectrometer ISOLTRAP at ISOLDE/CERN play an important role. Status and recent results on mass measurements of radioactive nuclides with ESR and ISOLTRAP are summarized.

Radioactive effluents, Portsmouth Uranium Enrichment Complex, calendar year 1983

International Nuclear Information System (INIS)

Acox, T.A.; Klein, L.S.

1984-03-01

Radioactive discharges from the Portsmouth Uranium Enrichment Complex are discussed and tabulated. Tables indicate both the location of the discharge and the nuclides discharged. Routine discharges for 1983 are well below the Radioactive Concentration Guide limits specified in DOE Order 5480.1, Chapter XI. There was, however, an unplanned release in December from the X-326 Building Side Purge which exceeded the limits. 1 figure

Characterization on incineration residue of radioactive solid wastes

International Nuclear Information System (INIS)

Katoh, Kiyoshi; Hirayama, Katsuyoshi; Kato, Akira.

1989-01-01

Characterization was carried out on incineration residue discharged from the radioactive solid waste incineration unit (capacity, 100 kg/h) in use at the Tokai Research Establishment of Japan Atomic Energy Research Institute (JAERI) to obtain basic data for investigating solidification methods of the residue. The characterized residue was taken from furnace and a primary ceramic filter of the incineration unit which incinerates combustible solid wastes generated at JAERI and the outside organizations. Items of characterization involve a particle size distribution, misplaced materials content, ignition loss, chemical composition and radioactivity of nuclides in the ash. As the results, the size of ash sampled from the furnace distributed a wide range, with about 35∼60 % of ash smaller than 5 mm and about 10∼25 % of massive one larger than 30 mm (max. size: ∼130 mm). The ignition loss was 2∼3 %. The chemical compositions of the ash were mainly SiO 2 , Fe 2 O 3 , CaO and Al 2 O 3 . The specific activities of the ash were about 0.4∼4 x 10 3 Bq/g, and principal contaminants were 60 Co and 137 Cs. (author)

DOSEmanPRO - active electronic online personal air sampler for detection of radon progeny long lived alpha nuclides

International Nuclear Information System (INIS)

Streil, T.; Oeser, V.

2002-01-01

Full text: Using the micro system - technology we developed a online personal air sampler not bigger than a mobile phone, to open a new dimension in personal dosimetry of inhaled radioactive aerosols. The DOSEman PRO containing an internal pump with a continuous air flow of 0.15 I/min sample the radon progeny or other nuclides on a millipore filter with excellent spectroscopic resolution. A 1.5 cm 2 light protected ion-implanted silicon detector analyses the alpha radiation at the filter. This small detector head contains also the pre amplification and pulse processing. The alpha radiation of the radon progeny and the long lived alpha nuclides is analyzed by a 60 channel spectrometer. The energy resolution of the online analyzed filter spectra is in the order of 150 keV. Mechanical and electronic design enables one to distinguish the long lived alpha nuclides from the radon and thoron progeny very easily. Using a special algorithm we correct the influence of the tailing of the radon progeny to the long lived alpha nuclides and take into consideration possible interference in determining the long lived alpha nuclides. Because of the air sampling volume of nearly 10 I/h, the system has a high efficiency. The detection limit by 2 hours sampling time is 0.05 Bq/m 3 alpha nuclide concentration. In a modified device for air sampling especially of long-lived alpha nuclides like uranium, radium or plutonium, the flow rate is increased to 0,3 1/min e.g. during a 10 h sampling period we can detect 0.005 Bq/m 3 in a low radon atmosphere. Assuming increased radon progeny concentration, the statistical error for the long lived alpha nuclides will be higher, but in most of the cases for use in nuclear facilities low radon concentrations are ambient conditions. This concept of an electronic personal air sampler with an alpha spectroscopy offers some outstanding advantages compared to passive dosimeters or off-line alpha air filters: The dose value and the nuclide concentration is

Nuclides Economy

International Nuclear Information System (INIS)

Ivanov, Evgeny; Subbotin, Stanislav

2007-01-01

Traditionally the subject of discussion about the nuclear technology development is focused on the conditions that facilitate the nuclear power deployment. The main objective of this work is seeking of methodological basis for analysis of the coupling consequences of nuclear development. Nuclide economy is the term, which defines a new kind of society relations, dependent on nuclear technology development. It is rather closed to the setting of problems then to the solving of them. Last year Dr. Jonathan Tennenbaum published in Executive Intelligence Review Vol. 33 no 40 the article entitled as 'The Isotope Economy' where main interconnections for nuclear energy technologies and their infrastructure had been explained on the popular level. There he has given several answers and, therefore, just here we will try to expand this concept. We were interested by this publication because of similarity of our vision of resource base of technologies development. The main paradigm of 'Isotope economy' was expresses by Lyndon H. LaRouche: 'Instead of viewing the relevant resources of the planet as if they were a fixed totality, we must now assume responsibility of man's creating the new resources which will be more than adequate to sustain a growing world population at a constantly improved standard of physical per-capita output, and personal consumption'. We also consider the needed resources as a dynamic category. Nuclide economy and nuclide logistics both are needed for identifying of the future development of nuclear power as far we follow the holistic analysis approach 'from cave to grave'. Thus here we try to reasoning of decision making procedures and factors required for it in frame of innovative proposals development and deployment. The nuclear power development is needed in humanitarian scientific support with maximally deep consideration of all inter-disciplinary aspects of the nuclear power and nuclear technologies implementation. The main objectives for such

Analysis of spatial distribution and inventory of radioactivity within the uranium mill tailings impoundment

Directory of Open Access Journals (Sweden)

D. O. Bugai

2015-10-01

Full Text Available Results are presented of the characterization of radioactivity inventory of Zapadnoe uranium mill tailings impoundment situated at Pridneprovsky Chemical Plant (PChP; Dneprodzerzhinsk, Ukraine. Analyses of radioactivity data set based on analytical studies of core material from 15 characterization boreholes allowed significantly refining waste volume and radioactivity inventory estimates. Geostatistical analyses using variogram function have established that radioactivity distribution in Zapadnoe tailings is characterized by regular spatial correlation patterns. Ordinary kriging method was applied to assess distribution of radioactivity in 3D. Results of statistical analyses suggest significant redistribution of uranium in the dissolved form in the residues (presumably due to water infiltration process. The developed structural model for radioactivity distribution is used for further risk assessment analyses. Derived radioactivity correlation scales can be used for optimization of sample collection when characterizing the PChP Site and similar contaminated sites elsewhere.

Summary report on the 1985 United Kingdom radioactive waste inventory

International Nuclear Information System (INIS)

Fletcher, A.M.; Wear, F.J.; Haselden, H.; Shepherd, J.; Tymons, B.J.

1986-04-01

Stocks of radioactive waste in the United Kingdom which have arisen, or are projected to arise, from commercial nuclear power reactors and fuel cycle facilities, research, medical and industrial uses of radioactive nuclides are given in the form of summary tables. Projected future arisings from operation and decommissioning of facilities and notional nuclear power generation programmes to 2030 are also given. (author)

The MacNuclide nuclear data environment

International Nuclear Information System (INIS)

Stone, C.A.

1992-01-01

Advance in technology have produced intriguing tools that can be applied to problems in nuclear science. Information management in nuclear science is an example of how technology is not quickly exploited. The U.S. Department of Energy supports an extensive program to evaluate published nuclear properties and store them in an electronic data base. Much of the evaluation effort has focused on producing the journal Nuclear Data Sheets and the publication Table of Isotopes. Although the electronic data base can itself be a valuable source of information, the software used to access is was designed using decades-old technologies. The authors of this paper have developed a novel data-base management system for nuclear properties. The application is known as MacNuclide. It is a nuclear data-base environment that uses the highly interactive and intuitive windowing environmentsof desk-top computers. The environment is designed around that image of the chart of nuclides. Questions are posed to the data base by placing constraints on properties and defining collections of nuclides to be used in data-base seraches. Results are displayed either as a simple list of nuclides that meet the imposed constraints or as a color chart of nuclides

Radioactive kryptonates in the analysis of environmental samples

International Nuclear Information System (INIS)

Tolgyessy, J.

1986-01-01

The term ''radioactive Kryptonates'' is used for substances into which atoms or ions of the radioactive nuclide 85 Kr are incorporated. The basis of the use of radioactive Kryptonates in analytical chemistry is that during a chemical reaction the crystalline lattice of the kryptonated carrier is destroyed, the carrier consumed, and the radioactive krypton released (radio-release method). Analysis can be made with a calibration curve or by comparison with a standard. Radio-release methods with the aid of radioactive Kryptonates as analytical reagents are very useful for the analysis of environmental samples, e.g. for the determination of air pollutants (ozone, sulphur dioxide, fluorine, hydrogen fluoride, mercury); and water pollutants (oxygen, dichromate, vanadium, hydrochloric acid, sulphur dioxide). (author)

Fukushima-derived fission nuclides monitored around Taiwan: Free tropospheric versus boundary layer transport

Science.gov (United States)

Huh, Chih-An; Hsu, Shih-Chieh; Lin, Chuan-Yao

2012-02-01

The 2011 Fukushima nuclear accident in Japan was the worst nuclear disaster following the 1986 Chernobyl accident. Fission products (nuclides) released from the Fukushima plant site since March 12, 2011 had been detected around the northern hemisphere in about two weeks and also in the southern hemisphere about one month later. We report here detailed time series of radioiodine and radiocesium isotopes monitored in a regional network around Taiwan, including one high-mountain and three ground-level sites. Our results show several pulses of emission from a sequence of accidents in the Fukushima facility, with the more volatile 131I released preferentially over 134Cs and 137Cs at the beginning. In the middle of the time series, there was a pronounced peak of radiocesium observed in northern Taiwan, with activity concentrations of 134Cs and 137Cs far exceeding that of 131I during that episode. From the first arrival time of these fission nuclides and their spatial and temporal variations at our sampling sites and elsewhere, we suggest that Fukushima-derived radioactive nuclides were transported to Taiwan and its vicinity via two pathways at different altitudes. One was transported in the free troposphere by the prevailing westerly winds around the globe; the other was transported in the planetary boundary layer by the northeast monsoon wind directly toward Taiwan.

Application of Micro-coprecipitation Method to Alpha Source Preparation for Measuring Alpha Nuclides

International Nuclear Information System (INIS)

Lee, Myung Ho; Park, Jong Ho; Oh, Se Jin; Song, Byung Chul; Song, Kyuseok

2011-01-01

Among the source preparations, an electrodeposition is a commonly used method for the preparation of sources for an alpha spectrometry, because this technique is simple and produces a very thin deposit, which is essential for a high resolution of the alpha peak. Recently, micro-coprecipitation with rare earths have been used to yield sources for -spectrometry. In this work, the Pu, Am and Cm isotopes were purified from hindrance nuclides and elements with an a TRU resin in radioactive waste samples, and the activity concentrations of the Pu, Am and Cm isotopes were determined by radiation counting methods after alpha source preparation like micro coprecipitation. After the Pu isotopes in the radioactive waste samples were separated from the other nuclides with an anion exchange resin, the Am isotopes were purified with a TRU resin and an anion exchange resin or a TRU resin. Activity concentrations and chemical recoveries of 241 Am purified with the TRU resin were similar to those with the TRU resin and anion exchange resin. In this study, to save on the analytical time and cost, the Am isotopes were purified with the TRU resin without using an additional anion exchange resin. After comparing the electrodeposition method with the micro-coprecipitation method, the micro-coprecipitation method was used for the alpha source preparation, because the micro-coprecipitation method is simple and more reliable for source preparation of the Pu, Am and Cm isotopes

The sorption of 210Pb, 210Bi and 210Po on montmorillonite: a study with emphasis on reversibility aspects and on the effect of the radioactive decay of adsorbed nuclides

International Nuclear Information System (INIS)

Ulrich, H.J.; Degueldre, C.

1993-01-01

The influence of the ionic strength and of pH on the adsorption/desorption processes of Pb, Bi and Po on montmorillonite has been investigated. For Pb, a strong dependence of the adsorption and desorption processes on the ionic strength was observed at pH d ) are measured. They range from 10 3 to 10 5 ml . g -1 for Pb and from 10 4 to 10 7 ml . g -1 for 210 Bi and 210 Po. When adsorption and desorption coefficients are compared, an agreement is found for both adsorption/desorption R d 's of Pb, whereas, for Bi and Po adsorption R d 's were several orders of magnitude lower than those obtained for desorption. The chemical activities of free Bi and Po in the liquid phase are limited by the formation of Bi and Po-colloids prior to the sorption step. This fact could explain the differences in the R d values. While the adsorption of Pb was reversible, only very small amounts of BI and Po could be desorbed from the montmorillonite (quasi-irreversible adsorption). The radioactive decay of adsorbed 210 Pb to 210 Bi, which in turn decays to 210 Po, can lead to significant changes in the desorption behaviour of the daughter nuclides. Whereas the sorption is nearly irreversible if Bi and Po adsorb on montmorillonite from the aqueous phase, they desorb more easily if they are generated by the radioactive decay of adsorbed 210 Pb. The difference in the distribution coefficients R d is approximately one order of magnitude in the case of Po, and more than 2 orders of magnitude in the case of Bi. (orig.)

Measurement of cosmogenic nuclides in extraterrestrial material

International Nuclear Information System (INIS)

Nishiizumi, K.; Arnold, J.R.

1981-01-01

Meteorites are rocks and pieces of iron-nickel alloy which fall to earth from time to time. They were formed about 4.6 billion years ago when our solar system was started. Thus it has been said that meteorites are the Rosetta stones of our solar system. We use the long-lived radioactive nuclides produced by cosmic ray bombardment, to study the history of the meteorites and also the history of the cosmic rays. When we have these historical facts in our hads, we hope we will be able to understand better how the solar system works, and how it got started. We can also learn more about the nature and origin of the cosmic rays. The accelerator mass spectrometry method helps not only reduce sample size, in most cases by two or three orders of magnitude, but opens another set of cosmogenic nuclides which have not been measured yet. Already 10 Be (t/sub 1/2 = 1.6 x 10 6 y), 36 Cl (3.0 x 10 5 y) and 129 I (1.6 x 10 7 y) in meteorites have been measured by accelerator mass spectrometry [3, 4, 7, 10]. Possible new candidates for measurement in extraterrestrial materials are 26 Al (7.2 x 10 5 y), 41 Ca (1.3 x 10 5 y), 60 Fe (approx. 10 5 y) and 59 Ni (7.6 x 10 4 y). We hope also to measure 146 Sm (1.0 x 10 8 y) and 92 Nb

Radioactive liquid waste processing method

International Nuclear Information System (INIS)

Nishi, Takashi; Baba, Tsutomu; Fukazawa, Tetsuo; Matsuda, Masami; Chino, Koichi; Ikeda, Takashi.

1993-01-01

As an adsorbent used for removing radioactive nuclides such as cesium and strontium from radioactive liquid wastes generated from a reprocessing plant, a silicon compound having siloxane bonds constituted by silicon and oxygen and having silanol groups constituted by silicon, oxygen and hydrogen, or an inorganic material mainly comprising aluminosilicate constituted with silicon, oxygen and aluminum is used. In the adsorbent of the present invention, since silica main skeletons are partially decomposed in an aqueous alkaline solution to newly form silanol groups having a cation adsorbing property, pretreatment such as pH adjustment is not necessary. (T.M.)

A Nuclide Release Model for a Deep Well Scenario near a Repository

International Nuclear Information System (INIS)

Lee, Youn Myoung; Jung, Jong Tae; Choi, Jong Won

2010-01-01

Recently several template programs ready for the safety assessment of a high-level radioactive waste repository (HLW) and a low- and intermediate level radioactive waste repository (LILW) systems, that are conceptually modeled, have been developed by utilizing GoldSim and AMBER at KAERI. During the last few years, such template programs have been utilized for the evaluation of nuclide transports in the nearand far-field of a repository as well as transport through the biosphere under various normal and disruptive release scenarios with assumed data. The GoldSim program, another template program by which influence due to a well located very near to the repository has been modeled and evaluated for an assumed case in order to simulate the worst exposure scenario. This seems very useful to evaluate an accidental event a long time after closure of the repository has been developed and illustrated

Risk analysis of radioactive waste repository based on the time dependent hazard rate

International Nuclear Information System (INIS)

Chang, S.H.; Cho, W.J.

1984-01-01

For the probabilistic risk analysis of the radioactive high level waste repository, the simplified method based on the time dependent hazard rate is proposed. The obtained results are compared with those from the time independent hazard rate. The estimation of the failure probability of the waste repository through this method gives more conservative results, especially when the half-life of nuclide is larger and retardation factors of nuclide is smaller. (Auth.)

Cosmogenic nuclide shielding corrections determined via MCNPX radiation transport and spallation cross sections

Science.gov (United States)

Argento, D.; Reedy, R. C.; Stone, J. O.

2011-12-01

Cosmogenic Nuclides (CNs) are a critical new tool for geomorphology, allowing researchers to date Earth surface events and measure process rates [1]. Prior to CNs, many of these events and processes had no absolute method for measurement and relied entirely on relative methods. Reliable absolute measurement methods impact research constraining ice age extents and provide important climatic data via well constrained erosion rates, etc. [2]. Continuing to improve CN methods is critical for these sciences. Significant progress has been made in the last two decades in refining the method and reducing analytic uncertainties [1,3]. CRONUS-Earth, a collaboration of cosmogenic nuclide researchers, has been developing calibration data and scaling methods to provide a self-consistent platform for use in interpreting nuclide concentration values into geologic data. However, several aspects of the radiation cascade have been exceedingly difficult to measure empirically with either accuracy or spatial extent. One such aspect is the angular distribution of secondary cosmic rays that are energetic enough to produce cosmogenic nuclides via spallation. Researchers studying the angular distribution of such cosmic rays have usually described the distribution as (cos(Θ))^m. Currently, the standard corrections, assume an m of 2.3, which is based on very sparse data sets with very limited spatial and altitude variation [1,4,5]. Researchers using CNs must know the production rate at the sample location, and then make corrections for the portion of the sky that is blocked by nearby topography. If the shielding correction model currently used is too simplistic, this introduces error into the final results. In this study, a Monte Carlo method radiation transport code, MCNPX is used to model the Galactic Cosmic Ray (GCR) radiation impinging on the upper atmosphere and tracks the resulting secondary particles through a model of the Earth's atmosphere. Angle and energy distributions are

Simulation of decay processes and radiation transport times in radioactivity measurements

Energy Technology Data Exchange (ETDEWEB)

García-Toraño, E., E-mail: e.garciatorano@ciemat.es [Laboratorio de Metrología de Radiaciones Ionizantes, CIEMAT, Avda. Complutense 22, 28040 Madrid (Spain); Peyres, V. [Laboratorio de Metrología de Radiaciones Ionizantes, CIEMAT, Avda. Complutense 22, 28040 Madrid (Spain); Bé, M.-M.; Dulieu, C.; Lépy, M.-C. [CEA, LIST, Laboratoire National Henri Becquerel (LNE-LNHB), Bldg 602, PC111, 91191 Gif-sur-Yvette Cedex (France); Salvat, F. [Facultat de Física (FQA and ICC), Universitat de Barcelona, Diagonal 647, 08028 Barcelona (Spain)

2017-04-01

The Fortran subroutine package PENNUC, which simulates random decay pathways of radioactive nuclides, is described. The decay scheme of the active nuclide is obtained from the NUCLEIDE database, whose web application has been complemented with the option of exporting nuclear decay data (possible nuclear transitions, branching ratios, type and energy of emitted particles) in a format that is readable by the simulation subroutines. In the case of beta emitters, the initial energy of the electron or positron is sampled from the theoretical Fermi spectrum. De-excitation of the atomic electron cloud following electron capture and internal conversion is described using transition probabilities from the LLNL Evaluated Atomic Data Library and empirical or calculated energies of released X rays and Auger electrons. The time evolution of radiation showers is determined by considering the lifetimes of nuclear and atomic levels, as well as radiation propagation times. Although PENNUC is designed to operate independently, here it is used in conjunction with the electron-photon transport code PENELOPE, and both together allow the simulation of experiments with radioactive sources in complex material structures consisting of homogeneous bodies limited by quadric surfaces. The reliability of these simulation tools is demonstrated through comparisons of simulated and measured energy spectra from radionuclides with complex multi-gamma spectra, nuclides with metastable levels in their decay pathways, nuclides with two daughters, and beta plus emitters.

Nuclide transport of decay chain in the fractured rock medium: a model using continuous time Markov process

International Nuclear Information System (INIS)

Younmyoung Lee; Kunjai Lee

1995-01-01

A model using continuous time Markov process for nuclide transport of decay chain of arbitrary length in the fractured rock medium has been developed. Considering the fracture in the rock matrix as a finite number of compartments, the transition probability for nuclide from the transition intensity between and out of the compartments is represented utilizing Chapman-Kolmogorov equation, with which the expectation and the variance of nuclide distribution for the fractured rock medium could be obtained. A comparison between continuous time Markov process model and available analytical solutions for the nuclide transport of three decay chains without rock matrix diffusion has been made showing comparatively good agreement. Fittings with experimental breakthrough curves obtained with nonsorbing materials such as NaLS and uranine in the artificial fractured rock are also made. (author)

Hazards of radioactive nuclide and their migration and repair research status in the environment

International Nuclear Information System (INIS)

Shi Yuting

2014-01-01

This paper gives a systematic and comprehensive introduction of the source of the radionuclides in the environment and the harm it brings to human and ecological environment. Furthermore, It summarizes the basic nature and environmental characteristics of three typical nuclides, which are 235 U, 131 I, 90 Sr respectively. In the end, a review of the migration and repairmen of the radionuclides in the environment is given. This paper provides a reference for further study of the radionuclide migration and the phytoremediation of low level radionuclide contamination. (author)

Precise Mapping Of A Spatially Distributed Radioactive Source

International Nuclear Information System (INIS)

Beck, A.; Caras, I.; Piestum, S.; Sheli, E.; Melamud, Y.; Berant, S.; Kadmon, Y.; Tirosh, D.

1999-01-01

Spatial distribution measurement of radioactive sources is a routine task in the nuclear industry. The precision of each measurement depends upon the specific application. However, the technological edge of this precision is motivated by the production of standards for calibration. Within this definition, the most demanding field is the calibration of standards for medical equipment. In this paper, a semi-empirical method for controlling the measurement precision is demonstrated, using a relatively simple laboratory apparatus. The spatial distribution of the source radioactivity is measured as part of the quality assurance tests, during the production of flood sources. These sources are further used in calibration of medical gamma cameras. A typical flood source is a 40 x 60 cm 2 plate with an activity of 10 mCi (or more) of 57 Co isotope. The measurement set-up is based on a single NaI(Tl) scintillator with a photomultiplier tube, moving on an X Y table which scans the flood source. In this application the source is required to have a uniform activity distribution over its surface

Catalog of gamma-rays unplaced in radioactive decay schemes

International Nuclear Information System (INIS)

Narita, Tsutomu; Kitao, Kensuke.

1991-03-01

A catalog is made for gamma-rays emitted in decay of radioactive nuclides but not placed in their decay schemes. It consists of two tables. In Table 1, the number of these unplaced gamma-ray components by a nuclide is given together with the fraction of total intensity of these gamma-rays to that of all observed gamma-rays. In Table 2, the unplaced gamma-rays are arranged in order of increasing energy. Each line of this table contains the gamma-ray energy, intensity, nuclide identification, and energies and intensities of the most prominent gamma-rays from the decay of the radionuclides. This catalog is a compilation from Evaluated Nuclear Structure Data File (ENSDF) maintained by National Nuclear Data Center at Brookhaven National Laboratory, of at February 1990. (author)

Radioactivity in newspapers and information business papers

International Nuclear Information System (INIS)

Kobashi, Asaya

1997-01-01

The radioactivities of the naturally occurring radionuclides ( 226 Ra, 228 Ra, 228 Th and 40 K) and a fallout nuclide ( 137 Cs) in newspapers issued during 1990s in Japan and information business papers were determined by gamma-ray spectrometry to obtain information on radioactivity level of papers and the sources of radionuclides contained in papers. The concentrations of the naturally occurring radionuclides in the newspapers were low, whereas the 228 Ra and 228 Th contents of an information business paper were as high as 30 Bq kg -1 . Perhaps the thorium series nuclides contained in this information business paper was present in the kaolinite filler used in the paper. 137 Cs was detected in all the newspapers, while the radionuclide was not detected in the information business papers. The 137 Cs concentration in the newspaper ranged from 0.1 to 0.2 Bq kg -1 . Mechanical pulp was the main constituent of the newspapers, and 137 Cs in the newspapers was maybe brought with the mechanical pulp which kept a part of fallout 137 Cs contained in the material wood. The data obtained in this work may be useful to estimate radioactivity released from incinerators to the environment by burning waste paper. (author)

The nuclide inventory in SFR-1; Nuklidinventariet i SFR-1

Energy Technology Data Exchange (ETDEWEB)

Ingemansson, Tor [ALARA Engineering, Skultuna (Sweden)

2001-10-01

This report is an account for a project carried out on behalf of the Swedish Radiation Protection Authority (SSI): 'Nuclide inventory in SFR-1' (The Swedish underground disposal facility for low and intermediate level reactor waste). The project comprises the following five sub-projects: 1) Measuring methods for nuclides, difficult to measure, 2) The nuclide inventory in SFR-1, 3) Proposal for nuclide library for SFR-1 and ground disposal, 4) Nuclide library for exemption, and 5) Characterising of the nuclide inventory and documentation for SFL waste. In all five sub-projects long-lived activity, including Cl-36, has been considered.

Radioactivity and foods

International Nuclear Information System (INIS)

Olszyna Marzys, A.E.

1991-01-01

The purpose of this article is to describe and contrast two relationships between radiation and food-on the one hand, beneficial preservation of food by controlled exposure to ionizing radiation; and, on the other, contamination of food by accidental incorporation of radioactive nuclides within the food itself. In food irradiation, electrons or electromagnetic radiation is used to destroy microorganisms and insects or prevent seed germination. The economic advantages and health benefits of sterilizing food in this manner are clear, and numerous studies have confirmed that under strictly controlled conditions no undesirable changes or induced radioactivity is produced in the irradiated food. An altogether different situation is presented by exposure of food animals and farming areas to radioactive materials, as occurred after the major Soviet nuclear reactor accident at Chernobyl. This article furnishes the basic information needed to understand the nature of food contamination associated with that event and describes the work of international organizations seeking to establish appropriate safe limits for levels of radioactivity in foods. 14 refs, 4 tabs

WebCN: A web-based computation tool for in situ-produced cosmogenic nuclides

Energy Technology Data Exchange (ETDEWEB)

Ma Xiuzeng [Department of Physics, Purdue University, West Lafayette, IN 47907 (United States)]. E-mail: hongju@purdue.edu; Li Yingkui [Department of Geography, University of Missouri-Columbia, Columbia, MO 65211 (United States); Bourgeois, Mike [Department of Physics, Purdue University, West Lafayette, IN 47907 (United States); Caffee, Marc [Department of Physics, Purdue University, West Lafayette, IN 47907 (United States); Elmore, David [Department of Physics, Purdue University, West Lafayette, IN 47907 (United States); Granger, Darryl [Department of Earth and Atmospheric Sciences, Purdue University, West Lafayette, IN 47907 (United States); Muzikar, Paul [Department of Physics, Purdue University, West Lafayette, IN 47907 (United States); Smith, Preston [Department of Physics, Purdue University, West Lafayette, IN 47907 (United States)

2007-06-15

Cosmogenic nuclide techniques are increasingly being utilized in geoscience research. For this it is critical to establish an effective, easily accessible and well defined tool for cosmogenic nuclide computations. We have been developing a web-based tool (WebCN) to calculate surface exposure ages and erosion rates based on the nuclide concentrations measured by the accelerator mass spectrometry. WebCN for {sup 10}Be and {sup 26}Al has been finished and published at http://www.physics.purdue.edu/primelab/for{sub u}sers/rockage.html. WebCN for {sup 36}Cl is under construction. WebCN is designed as a three-tier client/server model and uses the open source PostgreSQL for the database management and PHP for the interface design and calculations. On the client side, an internet browser and Microsoft Access are used as application interfaces to access the system. Open Database Connectivity is used to link PostgreSQL and Microsoft Access. WebCN accounts for both spatial and temporal distributions of the cosmic ray flux to calculate the production rates of in situ-produced cosmogenic nuclides at the Earth's surface.

Questionnaire survey report on measurement of radioactivity in working environment of radioisotopes facility

International Nuclear Information System (INIS)

Kawano, Takao; Nomura, Kiyoshi

2008-01-01

To look over the current measurement of radioactivity concentration in working environment of many radioisotopes facilities, a questionnaire survey was carried out under the auspices of the Planning Committee of the Japan Society of Radiation Safety Management. 64 responses were obtained in 128 radiation facilities, which the questionnaires were sent to. The main results were obtained by aggregate analysis of the answers for questionnaires as the followings. Major nuclides subject to measurement were 3 H, 14 C, 32 P and 125 I Sampling of radioisotopes in air was mainly performed using collectors like dust samplers and HC-collectors. Liquid scintillation counters and gamma counters were used to measure β and γ radioactivity contained in airborne particles or gas samples. Contamination by radioactivity was not detected in 55% facilities surveyed, but in 40% facilities at the same level as or at lower levels than a hundredth part of the regulated concentration limit of each nuclide. Almost all facilities is found to consider that the measurement of radioactivity concentration in working environments is not always necessary. (author)

Bioremediation system on-line for removal radionuclides in radioactive waters; Sistema de biorremediation on-line pra la eliminacion de radionuclidos en aguas radiactivas

Energy Technology Data Exchange (ETDEWEB)

Belinchon, J. A.; Garcia, A. M.; Ruibal, C.; Moreno, D. A.

2010-07-01

In previous studies developed in Cofrentes Nuclear Power Plant (Valencia, Spain), has been observed that the microorganisms in the radioactive waters of the spent nuclear fuel pool are capable of colonizing the metallic surfaces of the walls and pipes and perform biofilm. These biofilm retain the nuclides contributing to decontaminate the water. In this project, carried out in Cofrentes Nuclear Power Plant, a pilot plant has been designed for the bio decontamination of the radioactive water. At present, the radioactive water coming from the spent nuclear fuel pools, pass through ionic exchange resins. After, these resins are managed as radioactive waste. In this project, the water passes through a bioreactor with stainless steel balls capable of being colonized by the microorganisms in the water. Inside the bioreactor the water gets in contact with the material of the balls, and a biofilm, which retains the nuclides in the water, is developed. The biofilm is easily removed by any conventional procedure of radiochemical decontamination of materials and the nuclides can be collected in a small volume for recovery final disposition or containment. Later, the material of the bioreactor could be managed as not radioactive material. (Author) 9 refs.

Radioactivity and Natural Radio nuclides Distribution in River Water, Coastal Water, Sediment and Eichornia Crassipes (Mart) Sloms and Their Accumulation Factor at Surabaya Area

International Nuclear Information System (INIS)

Agus Taftazani; Sumining; Muzakky

2002-01-01

Distribution of radioactivity and natural radionuclide in water, sediment and eichornia crassipes (mart) sloms from Surabaya river and coastal area have been evaluated. Five sampling locations were selected to represent fresh water and coastal water environment. The samples consist of water (fresh and coastal), bottom surface sediment and eichornia crassipes (mart) sloms The result showed that the gross-β activity from water environment were lower than the threshold value of Environmental Minister Act. Kep.02/MENKLH/I/1988 (1000 mBq/L) and indicated that β-radioecological quality of water were still good. But the activity of the gross-α of water environment were higher than the threshold value of Environmental Minister Act. Kep.02/MENKLH/I/1988 (100 mBq/L). The eichornia crassipes (mart) sloms (gross) activity were higher than water and sediment activities and indicated that transfer of radionuclides from water to sediment and organism can be detected in water environment. Two natural radionuclides can be identified by γ-Spectrometric technique, they were K-40 and TI-208. Generally the distribution factor F D were smaller than bioaccumulation factor F B . (author)

Algorithm improvement program nuclide identification algorithm scoring criteria and scoring application.

Energy Technology Data Exchange (ETDEWEB)

Enghauser, Michael [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

2016-02-01

The goal of the Domestic Nuclear Detection Office (DNDO) Algorithm Improvement Program (AIP) is to facilitate gamma-radiation detector nuclide identification algorithm development, improvement, and validation. Accordingly, scoring criteria have been developed to objectively assess the performance of nuclide identification algorithms. In addition, a Microsoft Excel spreadsheet application for automated nuclide identification scoring has been developed. This report provides an overview of the equations, nuclide weighting factors, nuclide equivalencies, and configuration weighting factors used by the application for scoring nuclide identification algorithm performance. Furthermore, this report presents a general overview of the nuclide identification algorithm scoring application including illustrative examples.

Development of scaling factor prediction method for radionuclide composition in low-level radioactive waste

International Nuclear Information System (INIS)

Park, Jin Beak

1995-02-01

Low-level radioactive waste management require the knowledge of the natures and quantities of radionuclides in the immobilized or packaged waste. U. S. NRC rules require programs that measure the concentrations of all relevant nuclides either directly or indirectly by relating difficult-to-measure radionuclides to other easy-to-measure radionuclides with application of scaling factors. Scaling factors previously developed through statistical approach can give only generic ones and have many difficult problem about sampling procedures. Generic scaling factors can not take into account for plant operation history. In this study, a method to predict plant-specific and operational history dependent scaling factors is developed. Realistic and detailed approach are taken to find scaling factors at reactor coolant. This approach begin with fission product release mechanisms and fundamental release properties of fuel-source nuclide such as fission product and transuranic nuclide. Scaling factors at various waste streams are derived from the predicted reactor coolant scaling factors with the aid of radionuclide retention and build up model. This model make use of radioactive material balance within the radioactive waste processing systems. Scaling factors at reactor coolant and waste streams which can include the effects of plant operation history have been developed according to input parameters of plant operation history

Ecological transport and radiation doses from ground water borne radioactive matters

International Nuclear Information System (INIS)

Bergman, R.; Bergstroem, U.; Evans, S.

1978-12-01

Turnover of radioactive matter entering the biosphere with ground water has been studied with regard to exposure and dose to critical groups and populations. The main alternatives considered for outflow of radioactive effluents to the biosphere are: outflow in a valley containing wells, outflow to a fresh-water lake, and outflow in a coastal region of the Baltic Sea. Mathematical models of a set of coupled ecosystems on local, regional- intermediate- and global levels have been used for calculations of doses. The intermediate system refers to the Baltic Sea. The mathematical analysis, based on first order kinetics for the exchange of matter in a system according to compartment principles, also includes products in decay chains, i.e. daughter nuclides generated by decay of nuclides under ecological cycling. The time dependent exposures have been studied for certain long-lived nuclides of radiological interest in waste from reprosessed fuel. Dose and dose commitment have been calculted for different release patterns comprising idealised episodes for outflow to the biosphere during short periods and outflow governed by constant leakage from a source on the border between geosphere and biosphere. (author)

Transuranium nuclides in the environment

International Nuclear Information System (INIS)

Sakanoue, Masanobu

1987-01-01

Many countries are presently concerned with problems relating to the safe disposal of nuclear waste containing various levels of transuranium nuclides. In this context, a review on the distribution and behaviour of transuranium elements in the environment studied at Kanazawa University in Japan is presented. About 17 years ago, a high degree of accumulation of 239 Pu in the surface soil of Nagasaki was found in the Nishiyama area, where 'black rain' occured just after the nuclear bomb explosion. The introduction of newly developed radiochemical methods and instrumentation has enabled studies to be carried out on environmental plutonium isotopes, americium-241 and more recently neptunium-237 with respect to distribution depth profile, variation with time and relationship with organic materials. Valuable information has been obtained on the basis of samples collected from various locations in Japan, including surface soil, sea and lake sediments, atmospheric aerosol, water from the Japan Sea and the Pacific Ocean, and from material related with the 'Bikini Event' of 1954. (orig.)

Man-made radioactivity of surface air and precipitation Munich-Neuherberg 1970-1975

International Nuclear Information System (INIS)

Hoetzl, H.; Rosner, G.; Winkler, R.

1976-07-01

The activity concentration of a number of artificial radionuclides and of Be 7 in surface air and the deposition of these nuclides to the ground by the precipitation is measured since 1970 resp. 1971 at Neuherberg near Munich. Air dust filters are compressed to give a pellet and precipitation is evaporated to a small volume before γ-spectrometry using a Ge(Li)-detector. After ashing of the samples Pusup(238, 239, 240) and Fe 55 are separated radiochemically and measured by alpha respectively X-ray spectrometry. The results, presented as monthly mean resp. sum values, are discussed and compared with results published by other authors (HASL, UKAEA, PTB, DWD a.o.). The contribution of artificial radioactivity to the radiation exposure from fallout nuclides during the years 1970 to 1975 was very low. Their concentration levels led to values of the annual intake, which are far beyond the admissible values according to the new Radiation Protection Ordinance of the FRG. With regard to the intake by inhalation Pu 239 is the most important of all observed nuclides, whereas in the case of ingestion Sr 90 is the critical nuclide. At this time the level of the activity concentration is mainly represented by the residual radioactivity from nuclear bomb tests. A continuous control is necessary because of the growth of nuclear power production and the increasing use of radionuclides. (orig.) [de

Research and Development of Technologies for Partitioning and Transmutation of Long-lived Nuclides in Japan - Status and Evaluation

International Nuclear Information System (INIS)

Sanae Aoki

2003-01-01

Japanese basic policy regarding disposal of high-level radioactive waste (HLW) is to solidify it into stabilized form, to store it for 30-50 years to be cooled, and to dispose of it deep to the underground (geological disposal). In Japan, reference to P and T technology for long-lived and other nuclides first appeared in the Long-term Programme for Nuclear Research, Development and Utilisation (or 'long-term nuclear programme') back in 1972. That programme noted the need for research and development in order to ensure effective processing of radioactive waste. The long-term nuclear programme issued in 1987 stated that P and T technology was very important from the viewpoint of recycling HLW and enhancing disposal efficiency. It also stated that systematic R and D would be carried out jointly by JAERI, the Power Reactor and Nuclear Fuel Development Corp. (PNC, now JNC) and others. The long-term nuclear programme issued in 1994 stated that each research institute would carry out basic studies on P and T technologies and evaluate each technology at some time in the mid- 1990's to determine how to proceed thereafter. Based on the evaluation schedule stated in this program, the AEC's Advisory Committee on Nuclear Fuel Cycle Back-end Policy investigated and considered matters concerning P and T technology for long-lived and other nuclides. In March 2000, the Committee issued a report entitled 'Research and Development of Technologies for Partitioning and Transmutation of Long-lived Nuclide Status and Evaluation Report'. A brief summary of this report is presented

Radioactivity and natural radionuclides distribution in river water, coastal water, sediment and Eichornia Crassipes (Mart) solms and their accumulation factor at Surabaya area

International Nuclear Information System (INIS)

Agus Taftazani; Sumining; Muzakky

2002-01-01

Distributions of radioactivity and natural radionuclides in water, sediment and eichornia crassipes (mart) solms from Surabaya River and coastal area have been evaluated. Five sampling locations were selected to represent fresh water and coastal water environment. The samples consist of water (fresh & coastal), bottom surface sediment and eichornia crassipes (mart) solms. The result showed that the gross-β activity from water environment were lower than the threshold value of Environmental Minister Act. Kep.02/MENKLH/I/1988 (1000 mBq/L) and indicated that β-radio ecological quality of water were still good. But the activity of the gross-α of water environment were higher than the threshold value of Environmental Minister Act. Kep.02/MENKLH/I/1988 (100 mBq/L). The eichornia crassipes (mart) solms (gross) activity were higher than water and sediment activities and indicated that transfer of radio nuclides from water to sediment and organism can be detected in water environment. Two natural radionuclide can be identified by γ-Spectrometric technique, they were K"4"0 and Tl"2"0"8. Generally the distribution factors F_D were smaller than bioaccumulation factor F_B. (author)

Measurements of airborne short-lived radioactivity concentration in a PET facility at a national University hospital

International Nuclear Information System (INIS)

Saito, Tadashi

2006-01-01

National universities in Japan became under regulation of Industrial Safety and Health Law since 2004FY. One of the legal obligations is working environment measurements such as airborne radioactivity concentration in the rooms where employees handle unsealed radiation sources. Both in 2004FY and in 2005FY, measurements of airborne radioactivity concentration were carried out by two different agencies. The most prominent difference among them is the measurement for short-lived PET nuclides. In 2004FY, one agency measured the radioactivity with a Ge spectrometer at its own laboratory, whereas, in 2005FY, the other agency brought a NaI scintillation counter for gross gamma counting to the Hospital. It can be shown that detection limits for short-lived PET nuclides are in principle almost the same in both methods. It is also found that, in the actual case, gamma spectrometry with a Ge spectrometer is superior in judgement of detection of the radioactivity. (author)

Use of bremsstrahlung information for the nondestructive characterization of radioactive waste packages; Nutzung von Bremsstrahlungsinformation zur zerstoerungsfreien Charakterisierung radioaktiver Abfallgebinde

Energy Technology Data Exchange (ETDEWEB)

Rohrmoser, Benjamin Paul

2016-11-10

In order to minimize pseudo activity whilst storage of radioactive waste packages it is required to determine the nuclide inventory as precisely as possible. The in Gamma spectra contained parts of bremsstrahlung can be used to identify and quantify certain beta nuclides. For this an analytical method has been developed. This was mainly tested with beta-emitter Sr-90 and Tm-170, as well as commonly present gamma-emitters in laboratory scale and actual 200 liter waste packages. As a result, non-destructive determination of radioactive wastes can be conducted more precisely.

Study on concentrating treatment test of simulated radioactive wastewater containing boron by reverse osmosis membrane in PWR NPP

International Nuclear Information System (INIS)

Ye Xinnan; Jiang Baihua; Fan Wenwen; Zhang Zhiyin; Yang Cangsheng

2015-01-01

The reverse osmosis membrane equipment in PWR NPP was employed to investigate the application of pilot scale system in the radioactive wastewater treatment at the full recirculation operation. The removal performance of the equipment for the boron and the radioactivity nuclide were studied, respectively. The experimental results show that the removal efficiency of the aromatic polyamide composite reverse osmosis membrane for boron is over 83.3% and the concentration of boron in concentrate is over 10000 mg/L. The experimental results also show that the removal efficiency of two nuclides including cobalt and cesium is over 97.9%. (authors)

NNDC Chart of Nuclides

International Nuclear Information System (INIS)

Sonzogni, A.

2008-01-01

The National Nuclear Data Center has recently developed an interactive chart of nuclides, http://www.nndc.bnl.gov/chart/, that provides nuclear structure and decay data. Since its implementation, it has proven to be one of the most popular web products. The information presented is derived from the ENSDF and Nuclear Wallet Card databases. Experimentally known nuclides are represented by a cell in chart with the number of neutrons on the horizontal axis and the number of protons on the vertical axis. The color of the cell is used to indicate the ground state half-life or the ground state predominant decay mode. (author)

Calibration of new measuring systems to detect emissions of radioactive noble gases

International Nuclear Information System (INIS)

Winkelmann, I.; Kreiner, H.J.

1977-12-01

This report describes the calibration of different systems for the integral measurement of radioactive noble gases and the calibration of a measuring chamber for the detection of individual nuclides of radioactive noble gases in the gaseous effluent of nuclear power plants. For these measuring chambers the calibration factors for Kr-85 and Xe-133 are given as well as the detection limits to be obtained with these measuring systems for several radioactive noble gases present in the gaseous effluent at the stack of nuclear power plants. Calibration factors for Kr-85 and Xe-133 and the detection limits of this measuring method for the detections of individual nuclides of radioactive noble gases in air samples are defined taken wirh a high pressure compressor in pressure flasks an measured on a Ge(Li)-semiconductor spectrometer (pressure flask measuring method). A measuring equipment is described and calibrated which allows simultaneous measurement of activity concentration of radioactive noble gases and radioactive aerosols with a sensitivity of 2 x 10 -7 Ci/m 3 for radioactive gases and 1 x 10 -9 Ci/m 3 for radioactive particulates at a background radiation of 1 R/h. This paper is an additional report to our STH-Bericht 3/76, 'Calibration of measuring equipment for monitoring of gaseous effluents from nuclear power plants', which specifies a procedure for the calibration of measuring chambers for monitoring of gaseous radioactive effluents from nuclear power plants /1/. The calibration system used here makes it possible to simultaneously calibrate several noble gas measuring devices. (orig.) [de

Accumulation and metabolism of radioactive nuclides

International Nuclear Information System (INIS)

Morita, Shigeki

1981-01-01

The distribution of 90 Sr and 137 Cs with a long effective half life showing relatively simple behaviors, into the fish was examined from the data of field work. 137 Cs tended to show higher coefficients of concentration in the order of shellfish, crustaceans and fishes in accordance with the food chain. If the concentration caused by the food chain was neglected, the biological half life was influenced by the body weight even among the same species of fish, and the coefficient of concentration showed differences due to growth and metabolic function. In comparison with stable Cs, the 137 Cs showed a coefficient of concentration 1.5 times that of 133 Cs in the fish muscle. With the exception of seaweeds, the distribution rate of 90 Sr was not so high, but its coefficient of concentration was higher than that of stable Sr in the fish muscle. However, the coefficient of concentration of stable Sr was higher in bones because of its slower metabolism. (Chiba, N.)

Integral test on activation cross section of tag gas nuclides using fast neutron spectrum fields

Energy Technology Data Exchange (ETDEWEB)

Aoyama, Takafumi; Suzuki, Soju [Power Reactor and Nuclear Fuel Development Corp., Oarai, Ibaraki (Japan). Oarai Engineering Center

1997-03-01

Activation cross sections of tag gas nuclides, which will be used for the failed fuel detection and location in FBR plants, were evaluated by the irradiation tests in the fast neutron spectrum fields in JOYO and YAYOI. The comparison of their measured radioactivities and the calculated values using the JENDL-3.2 cross section set showed that the C/E values ranged from 0.8 to 2.8 for the calibration tests in YAYOI and that the present accuracies of these cross sections were confirmed. (author)

Database on nuclide content of coal and gangue in Chinese coal mines

International Nuclear Information System (INIS)

Liu Fudong; Liao Haitao; Wang Chunhong; Chen Ling; Liu Senlin

2006-01-01

The designing ides, structure, interface and basic function of a database are introduced of nuclide content of coal or gangue in Chinese coal mine. The design of the database adopts Sybase database system, and the database has the functions of making inquiries of keyword, classification and statistics, printing, data input which are achieved by using Power builder Language program. At the present, in this database, the data are collected on the radioactivity of natural radionuclide of 2043 coal, gangue and the other relative samples from various coal miners of all over the country. The database will provide the basic data for the environmental impact assessment of Chinese coal energy. (authors)

Radioactivity of 210Pb in Japanese cigarettes and radiation dose from smoking inhalation

International Nuclear Information System (INIS)

Sakoda, A.; Fukao, K.; Kawabe, A.; Kataoka, T.; Hanamoto, K.; Yamaoka, K.

2012-01-01

It is well known that cigarette tobaccos contain naturally occurring radioactive nuclides such as 210 Pb and 210 Po. In many countries, the radioactivity of tobaccos has been measured to estimate the effective dose from smoking inhalation. The present study covered 24 cigarette brands including the top 20 of sales in Japan between April 2008 and March 2009. The activity concentrations of 210 Pb were measured by gamma-ray spectrometry, and then those of its progeny ( 210 Po) were evaluated assuming the radioactive equilibrium between the two nuclides. Their concentrations were in the range of 2-14 mBq cigarette -1 with an arithmetic mean of 8±3 mBq cigarette -1 . The annual committed effective doses were also calculated, based on the scenario that a smoker consumes 20 cigarettes a day. The average doses from 210 Pb and 210 Po inhalations were 22±9 and 68±27 uμSv y -1 , respectively. (authors)

Radioactivity and deep geothermal energy; Radioaktivitaet und tiefe Geothermie

Energy Technology Data Exchange (ETDEWEB)

Janczik, Sebastian; Kaltschmitt, Martin [Technische Univ. Hamburg-Harburg (Germany). Inst. fuer Umwelttechnik und Energiewirtschaft; Merkel, Broder [Technische Univ. Bergakademie Freiberg (Germany). Inst. fuer Geologie

2012-02-15

Due to recent developments in energy politics renewable energies get more and more importance in Germany. This is especially true for geothermal energy representing a promising option for the environmentally sound and secure generation of heat and electricity. But there are a lot of very emotional discussions due to radioactive residues and wastes produced by a geothermal plant. Thus this paper compares radioactivity resulting from geothermal energy with radioactivity coming from other natural sources. In doing so it becomes obvious that naturally radioactive sources exist in all parts of the ecosphere (i.e. air, water, soil). The paper shows also that the specific activities of radioactive elements from geothermal energy in form of residues and waste emerge from radioactive decay of nuclides and that their radiation is not higher than the radiation of other naturally occurring radioactive elements. (orig.)

Development of high-level radioactive waste treatment and conversion technologies 'Dry decontamination technology development for highly radioactive contaminants'

International Nuclear Information System (INIS)

Oh, Won Zin; Lee, K. W.; Won, H. J.; Jung, C. J.; Choi, W. K.; Kim, G. N.; Moon, J. K.

2001-04-01

The followings were studied through the project entitled 'Dry Decontamination Technology Development for Highly Radioactive Contaminants'. 1.Contaminant Characteristics Analysis of Domestic Nuclear Fuel Cycle Projects(NFCP) and Applicability Study of the Unit Dry-Decontamination Techniques A. Classification of contaminated equipments and characteristics analysis of contaminants B. Applicability study of the unit dry-decontamination techniques 2.Performance Evaluation of Unit Dry Decontamination Technique A. PFC decontamination technique B. CO2 decontamination technique C. Plasma decontamination technique 3.Development of Residual Radiation Assessment Methodology for High Radioactive Facility Decontamination A. Development of radioactive nuclide diffusion model on highly radioactive facility structure B. Obtainment of the procedure for assessment of residual radiation dose 4.Establishment of the Design Concept of Dry Decontamination Process Equipment Applicable to Highly Radioactive Contaminants 5.TRIGA soil unit decontamination technology development A. Development of soil washing and flushing technologies B. Development of electrokinetic soil decontamination technology

Low activation material design methodology for reduction of radio-active wastes of nuclear power plant

International Nuclear Information System (INIS)

Hasegawa, A.; Satou, M.; Nogami, S.; Kakinuma, N.; Kinno, M.; Hayashi, K.

2007-01-01

Most of the concrete shielding walls and pipes around a reactor pressure vessel of a light water reactor become low level radioactive waste at decommission phase because they contain radioactive nuclides by thermal-neutron irradiation during its operation. The radioactivity of some low level radioactive wastes is close to the clearance level. It is very desirable in terms of life cycle cost reduction that the radioactivity of those low level radioactive wastes is decreased below clearance level. In case of light water reactors, however, methodology of low activation design of a nuclear plant has not been established yet because the reactor is a large-scale facility and has various structural materials. The Objectives of this work are to develop low activation material design methodology and material fabrication for reduction of radio-active wastes of nuclear power plant such as reinforced concrete. To realize fabrication of reduced radioactive concrete, it is necessary to develop (1) the database of the chemical composition of raw materials to select low activation materials, (2) the tool for calculation of the neutron flux and the spectrum distribution of nuclear plants to evaluate radioactivity of reactor components, (3) optimization of material process conditions to produce the low activation cement and the low activation steels. Results of the data base development, calculation tools and trial production of low activation cements will be presented. (authors)

Porous structure analysis of radioactive spent resin cementation matrix

International Nuclear Information System (INIS)

Zhou Yaozhong; Yun Guichun

2004-01-01

According to a cement product microstructure, a radioactive spent resin cementation matrix has the properties of porous matters. The distributing of the pore size and the pore microstructure stability are closely related to many crucial macro properties, including strength and permeability of the matrixes. By using a new computer-controlled Hg pressure test, a experiment methods of the matrix micro-properties was studied. By using porous structure analyses, it was found that the experimental method is useful for the future cementation research. In this test, it was also found that ASC cement matrixes of spent resin have superior microstructure to the OPC's. They have better pore size distribution, more stable structure and higher ability to hold the Hg in the matrixes than OPC's, and these properties are the important factors that make ASC cement matrixes have more stable macro-structure and lower leaching of nuclides. (authors)

Nuclide content in reactor waste

International Nuclear Information System (INIS)

1981-11-01

Certain corrosion and fission products of importance in reactor waste management cannot be measured by gammaspectrometric techniques. In this study, a method is suggested by which the occurence of such nuclides can be quantitatively related to suitable gamma-emitters of similar origin. The method is tested by statistical analysis on the waste data recorded from two Swedish nuclear power plants. As this method is not applicable for Carbon-14, this nuclide was measured directly in spent ion exchange resins from three Finnish and Swedish power plants. (author)

Effect of background radiation shielding on natural radioactivity distribution measurement with imaging plate

International Nuclear Information System (INIS)

Mori, C.; Suzuki, T.; Koido, S.; Uritani, A.; Miyahara, H.; Yanagida, K.; Miyahara, J.; Takahashi, K.

1996-01-01

Distribution images of natural radioactivity contained in various natural materials such as vegetable, animal meat and pottery work can be obtained with an imaging plate which has high sensitivity for nuclear radiations. For such very low levels of radioactivity, natural background radiations must be reduced using a shielding box. The lining, on the inside of the box, with low atomic number material such as acrylic resin is very effective in reducing electrons, β-rays and low energy X- and γ-rays emitted from the inner surface of the shielding material. Some images of natural radioactivity distribution were obtained and the radioactivity, mainly 40 K, contained in natural materials was measured by using an HPGe detector and also the imaging plate itself. (orig.)

Chart of nuclides relating to neutron activation

International Nuclear Information System (INIS)

Okada, Minoru

1981-09-01

This chart is for frequent use in the prediction of the product species of neutron activation. The first edition of the chart has been made in 1976 after the repeated trial preparation. It has the following good points. (1) Any letter in chart is as large as one can read easily. [This condition has been obtained by the selection of items to be shown in chart. They are the name (the symbol of element, mass number, and half-life) of nuclide or of isomer, and the type of decay.]. (2) Decay product has been shown indirectly for branchings with two-step decay via short-lived daughter in an excited state. [This matter has been realized by use of the new mode of indication.] (3) Nuclides shown in chart are (a) naturally occurring nuclides and (b) nuclides formed from naturally occurring nuclides through one of the following reactions: (n, γ), (n, n'), (n, p), (n, α), (n, 2n), (n, pn), (n, 3n), (n, αn), (n, t), (n, 3 He), (n, 2p), and (n, γ)(n, γ). In the revision of the first edition, some modes of indication have become a little simpler, and the isomers of shorter half-lives (0.1 - 1 μs) have been added. (author)

Correlation of radon and thoron concentrations with natural radioactivity of soil in Zonguldak, Turkey

Science.gov (United States)

Koray, Abdullah; Akkaya, Gizem; Kahraman, Ayşegül

2017-02-01

Radon and thoron gases are produced by the decay of the radioactive elements those are radium and thorium in the soil. In this study, the correlations between soil radon and thoron concentration with their parent nuclide (226Ra and 232Th) concentrations in collected soil samples from the same locations were evaluated. The result of the measurement shows that the distribution of radon and thoron in soil showed the same tendency as 226Ra and 232Th distribution. It was found a weak correlation between the radon and the 226Ra concentration (R =0.57), and between the thoron and the 232Th concentration (R=0.64). No strong correlation was observed between soil-gas radon and thoron concentration (R = 0.29).

Nuclides for radiotherapy: an overview

International Nuclear Information System (INIS)

Andres, R.Y.; Blattmann, H.

1986-02-01

With the emergence of new, biological vehicles of great organ specificity (e.g. steroid hormones, antibodies) the concept of systemic tumor therapy with the aid of radiotherapeutica has gained new momentum. In order to assess the options open for optimal adaptation of the radiation properties to the pharmacocinetics of a vehicle, a search was done to identify potentially useful therapeutic radionuclides. Main criteria for selection were half life, low gamma-yield and stable daughter nuclide. The resulting possibilities fall into 4 categories: 1) alpha-emitters (At-211); 2) beta/sup -/-emitters that can be prepared in a carrierfree fashion (P-32, S-35, As-77, Y-90, Ag-111, Pm-149, Tb-161, Lu-177), 3) beta/sup -/-emitters with carrier added (Pd-109, Pr-142, Gd-159, Er-169, Tm-172, Yb-175, Re-188, Ir-194, Pt-197) and 4) electron capture nuclides, emitting Auger-cascades (Cr-51, Ga-67, Ge-71, Br-77, Ru-97, Sb-119, I-123, Cs-129, Nd-140, Er-165, Ta-177, Hg-197, Tl-201). Among the 4th group some well known, diagnostically used nuclides are found. Their therapeutic use necessitates the precise localisation in or very near the genetic material of the cell to be killed; only there the destructive power of the very short range Auger-electrons can be used. For each of the selected nuclides a summary of decay data, possibilities of preparation and chemical reactivity for labelling of vehicles is given. (author)

Scaling factors for the activity determination of radioactive waste from nuclear power reactors

International Nuclear Information System (INIS)

Medici, Marcela A.; Piumetti, Elsa H.

2007-01-01

Specific information of the total activity and activity concentration of the radionuclides contained is required for conditioning, transporting and final disposal of radioactive waste. Due to the complexity associated to alpha and beta measurements for these emitters it is worldwide used, particularly in the case of heterogeneous radioactive waste, the Scaling Factor Method. As in other cases, inputs of the results of the analysis of waste samples taking from waste streams are necessary. The Scaling Factor Method is based on the determination of averaged correlations between the activity concentrations of Difficult to Measure (DTM) nuclides (i.e. alpha and beta emitters) and the activity concentration of easy to measure nuclides (i.e. strong gamma emitters) called Key Nuclides (KN). In the application of this method two phases may be identified: in the first one the degree of correlation between averaged activities of DTM and a given KN is verified, and specific Scaling Factors are derived for every DTM radionuclide. In the second stage the total activity and the activity concentration of the selected KN is determined in each waste item and, by applying the SFs obtained previously, the activities of DTM nuclides are calculated. It is concluded that this method is appropriate and cost-effective and it is stressed that it is only applicable while the Nuclear Power Reactor is in operation. (author)

Suitability study of using a coincidence monitor for room air radioactivity monitoring in a PET center

International Nuclear Information System (INIS)

Roellig, D.; Reichelt, C.; Iwatschenko-Borho, M.

2001-01-01

The application of radioactive nuclides in medicine may cause as well radioactive exposure of personnel (Medical Technical Assistants). In the present case the exposure of personnel in the area of medical positron-emission tomography (PET) within the Research Center of Rossendorf due to exhalation of the injected activity by the patient shall be investigated. For this purpose it is necessary to measure the activity concentration of the room air. Conventional methods such as collecting samples on special filters are not suitable due to the short half-life time of the used nuclides. Standard type continuous monitors are hardly suitable as well, because the injected activity of the patient and various radioactive sources required for the calibration of the PET-Camera produce an increased gamma background. In order to eliminate these disturbing influences a monitor has been constructed which uses CCM (cobalt coincidence method) developed by the company Thermo Eberline ESM. This method is specially suitable because upon each radioactive decay of PET nuclides positrons are emitted which in turn annihilate via the simultaneous emission of two 511 keV gamma quanta under an angle of 180 . The air to be measured is sucked through a cavity with two scintillation detectors on opposite sides. The coincident pulses produced by annihilating positrons inside the cavity are counted by a suitable electronic. Gamma quanta from outside the cavity can produce a pulse only in one detector and are rejected. Therefore no heavy lead shielding is required. Besides the mechanical construction of the monitor optimization and calibration for different PET-nuclides had to be performed. Special attention was paid to the sampling system. The air intake had to be close to the breathing zone of the MTA. The hose to the monitor had to be as short as possible. The target of the work was to design a model for an industrial monitor. (orig.) [de

Monitoring of radioactivity in the environs of Finnish nuclear power stations in 1987

International Nuclear Information System (INIS)

Sjoeblom, K.-L.; Klemola, S.; Ilus, E.; Arvela, H.; Blomqvist, L.

1989-06-01

Results of the environmental programmes for monitoring radioactive contamination around Finnish nuclear power plants in 1987 are reported. Fallout from the Chernobyl accident, which took place in April 1986, was still dominating the artificial radiation situation in Finland. Thus, large amounts of 137 Cs and other long-lived fallout nuclides predominated in the environmental samples taken in the vicinity of nuclear power plants. The extremely small airborne releases from Finnish nuclear power plants were almost totally covered by fallout nuclides. The somewhat higher aquatic releases were easier to distinguish, and it was possible to follow their spread in the marine environment. The contribution of locally discharged nuclides to radiation doses of the population was insignificant

Computer programs to make a Chart of the nuclides for WWW

International Nuclear Information System (INIS)

Nakagawa, Tsuneo; Katakura, Jun-ichi; Horiguchi, Takayoshi

1999-06-01

Computer programs to make a chart of the nuclides for World Wide Web (WWW) have been developed. The programs make a data file for WWW chart of the nuclides from a data file containing nuclide information in the format similar to ENSDF, by filling unknown half-lives with calculated ones. Then, the WWW chart of the nuclides in the gif format is created from the data file. The programs to make html files and image map files, to select a chart of selected nuclides, and to show various information of nuclides are included in the system. All the programs are written in C language. This report describes the formats of files, the programs and 1998 issue of Chart of the Nuclides made by means of the present programs. (author)

Radioactivity of fishes contaminated by nuclear-bomb test explosions with special reference to the nuclides

Energy Technology Data Exchange (ETDEWEB)

Mori, T; Saiki, M

1957-01-01

The nuclides formerly found in contaminated fish are /sup 89/Sr, /sup 90/Sr, /sup 90/Y, /sup 32/P, /sup 137/Cs, and /sup 106/Ru in bones and scales and /sup 137/Cs, /sup 106/Ru, /sup 144/Ce, /sup 144/Pr, /sup 95/Zr, and /sup 95/Nb in viscera and muscles. Moreover the following were found newly by M. and S.: /sup 65/Zn, /sup 113m, 115/Cd, /sup 55/ /sup 59/Fe, /sup 54/Mn, /sup 140/Ba, and /sup 140/La in viscera and muscles.

Determination of natural radioactive elements in Abo Zaabal, Egypt by means of gamma spectroscopy

International Nuclear Information System (INIS)

Morsy, Zeinab; Abd El-Wahab, Magda; El-Faramawy, Nabil

2012-01-01

Highlights: ► We examined the radioactivity of different type samples from Abo Zaabaal Lake. ► We evaluated the natural nuclide gamma-ray activities and their annual dose rates. ► We evaluated the concentrations of 226 Ra and its hazard indices. ► We assessed the absorbed dose in human. ► All results are within normal ranges. - Abstract: The natural nuclide gamma-ray activities and their respective annual effective dose rates, produced by 238 U, 232 Th, 40 K and 226 Ra, are determined for 10 different natural samples (soil–plant–water) from Abo Zaabaal Lake. This lake is located very close to the Egyptian reactors. The gamma spectra analysis indicates that the photo-gamma lines represent ten radioactive nuclides 234 Th, 239 Pu, 228 Ac, 226 Ra, 212 Pb, 214 Pb, 208 Tl, 212 Bi, 214 Bi and 40 K. These nuclides represent the daughters of the natural radioactive series 238 U and 232 Th with 40 K. The mean activity concentration of 238 U was found to be 6.57, 10.16 and 5.44 Bq kg −1 for (soil–plant–water); 8.46, 8.33 and 6.04 Bq kg −1 of 232 Th, and 136.3, 216.8 and 119.2 Bq kg −1 of 40 K respectively. The mean activity concentrations of 226 Ra were obtained which help to evaluate the radiation hazard indices as radium equivalent, internal and external hazard indices. In addition, to assess the radiation risk to a biosystem, the annual effective dose rate, the absorbed dose in human and the absorbed dose outdoor are also evaluated.

Development of monitor for multiple beta-ray nuclides in liquid radioactive waste (IV)

Energy Technology Data Exchange (ETDEWEB)

Kim, Chang Kyu; Nam, Uk Won; Seon, K. I.; Kong, K. N.; Son, J. D.; Chin, H.; Park, J. H.; Yuk, I. S.; Han, W. Y. [Korea Astronomy and Space Science Institute, Daejeon (Korea, Republic of)

2004-02-15

In the 4{sup th} fiscal year, the performance of the system developed in previous year have been stablilized. An automatic mixer system to mix the liquid radioactive waste with the liquid scintillator was designed and manufactured to make continuous monitoring possible. Mechanical systems for the automatic transfer, injection of radioactive samples, and for sealing sample bottle and its attachment on detector system have been designed and developed for completely integrated system, The experimental has been performed for the radioactive analysis by using the system. The measured data are transferred to central computer, which controls the monitoring system, through the RS-232 communication protocol. A software for host personal computer was developed for the control and analysis of the integrated system.

Distribution of residual long-lived radioactivity in the inner concrete walls of a compact medical cyclotron vault room.

Science.gov (United States)

Fujibuchi, Toshioh; Nohtomi, Akihiro; Baba, Shingo; Sasaki, Masayuki; Komiya, Isao; Umedzu, Yoshiyuki; Honda, Hiroshi

2015-01-01

Compact medical cyclotrons have been set up to generate the nuclides necessary for positron emission tomography. In accelerator facilities, neutrons activate the concrete used to construct the vault room; this activation increases with the use of an accelerator. The activation causes a substantial radioactive waste management problem when facilities are decommissioned. In the present study, several concrete cores from the walls, ceiling and floor of a compact medical cyclotron vault room were samples 2 years after the termination of operations, and the radioactivity concentrations of radionuclides were estimated. Cylindrical concrete cores 5 cm in diameter and 10 cm in length were bored from the concrete wall, ceiling and floor. Core boring was performed at 18 points. The gamma-ray spectrum of each sample was measured using a high-purity germanium detector. The degree of activation of the concrete in the cyclotron vault room was analyzed, and the range and tendency toward activation in the vault room were examined. (60)Co and (152)Eu were identified by gamma-ray spectrometry of the concrete samples. (152)Eu and (60)Co are produced principally from the stable isotopes of europium and cobalt by neutron capture reactions. The radioactivity concentration did not vary much between the surface of the concrete and at a depth of 10 cm. Although the radioactivity concentration near the target was higher than the clearance level for radioactive waste indicated in IAEA RS-G-1.7, the mean radioactivity concentration in the walls and floor was lower than the clearance level. The radioactivity concentration of the inner concrete wall of the medical cyclotron vault room was not uniform. The areas exceeding the clearance level were in the vicinity of the target, but most of the building did not exceed the clearance levels.

In Depth Modeling of Nuclide Transport in the Geosphere and the Biosphere to Reduce Uncertainty (Final Report)

International Nuclear Information System (INIS)

Lee, Youn Myoung; Kang, Chul Kyung; Hwang, Yong Soo; Lee, Sung Ho

2010-08-01

The Korea Radioactive Waste Management Center (KRMC) is conducting a research on a step by step development of a safety case for the Gyeongju low- and intermediate-level radioactive waste repository (WNEMC; Wolseong Nuclear Environment Management Center). A modeling study and development of a methodology, by which an assessment of safety and performance for a low- and intermediate level radioactive waste (LILW) repository could be effectively made has been carried out. With normal or abnormal nuclide release cases associated with the various FEPs and scenarios involved in the performance of the proposed repository in view of nuclide transport and transfer both in geosphere and biosphere, a total system performance assessment (TSPA) program has been developed by utilizing such commercial development tool programs as GoldSim, AMBER, MASCOT-K, and TOUGH2 in Korea Atomic Energy Research Institute (KAERI) under contract with KRMC. The final project report especially deals much with a detailed conceptual modeling scheme by which a GoldSim program modules, all of which are integrated into a TSPA program template kit as well as the input data set currently available. In-depth system models that are conceptually and rather practically described and then ready for implementing into a GoldSim TSPA program are introduced with plenty of illustrative conceptual schemes and evaluations with data currently available. The GoldSim TSPA tempalte program and the AMBER biosphere tempalte program as well as the TOUGH-2 gas migration template program developed through this project are expected to be successfully applied to the post closure safety assessment required for WNEMC by the regulatory body with increased practicality and much reduced uncertainty and conservatism

Transient temperature distributions in geological media surrounding radioactive waste repositories

Energy Technology Data Exchange (ETDEWEB)

Beyerlein, S W; Sunderland, J E [Massachusetts Univ., Amherst (USA). Dept. of Mechanical Engineering

1981-01-01

Closed form analytical solutions are presented for the transient temperature distributions resulting from underground radioactive waste disposal. The thermal source term is represented by point or spherical sources whose strength decreases exponentially with time. The transient temperature distributions can be determined above the disposal horizon over a time interval of hundreds of years.

A computer program to calculate nuclide yields in complex decay chain for selection of optimum irradiation and cooling condition

International Nuclear Information System (INIS)

Takeda, Tsuneo

1977-11-01

This report is prepared as a user's input manual for a computer code CODAC-No.5 and provides a general description of the code and instructions for its use. The code represents a modified version of the CODAC-No.4 code. The code developed is capable of calculating radioactive nuclide yields in an any given complex decay and activation chain independent of irradiation history. In this code, eighteen kinds of valuable tables and graphs can be prepared for output. They are available for selection of optimum irradiation and cooling conditions and for other intentions in accordance with irradiation and cooling. For a example, the ratio of a nuclide yield to total nuclide yield depending on irradiation and cooling times is obtained. In these outputs, several kinds of complex and intricate equations and others are included. This code has almost the same input forms as that of CODAC-No.4 code excepting input of irradiation history data. Input method and formats used for this code are very simple for any kinds of nuclear data. List of FORTRAN statements, examples of input data and output results and list of input parameters and its definitions are given in this report. (auth.)

Lognormal Distribution of Cellular Uptake of Radioactivity: Statistical Analysis of α-Particle Track Autoradiography

Science.gov (United States)

Neti, Prasad V.S.V.; Howell, Roger W.

2010-01-01

Recently, the distribution of radioactivity among a population of cells labeled with 210Po was shown to be well described by a log-normal (LN) distribution function (J Nucl Med. 2006;47:1049–1058) with the aid of autoradiography. To ascertain the influence of Poisson statistics on the interpretation of the autoradiographic data, the present work reports on a detailed statistical analysis of these earlier data. Methods The measured distributions of α-particle tracks per cell were subjected to statistical tests with Poisson, LN, and Poisson-lognormal (P-LN) models. Results The LN distribution function best describes the distribution of radioactivity among cell populations exposed to 0.52 and 3.8 kBq/mL of 210Po-citrate. When cells were exposed to 67 kBq/mL, the P-LN distribution function gave a better fit; however, the underlying activity distribution remained log-normal. Conclusion The present analysis generally provides further support for the use of LN distributions to describe the cellular uptake of radioactivity. Care should be exercised when analyzing autoradiographic data on activity distributions to ensure that Poisson processes do not distort the underlying LN distribution. PMID:18483086

A study of Radon-Concentration Distribution in Buildings in Gyeong-ju

Energy Technology Data Exchange (ETDEWEB)

Park, C. H.; Jang, S. Y.; Jung, O. J.; Moon, J. H. [Dongguk University, Gyeongju (Korea, Republic of)

2010-10-15

Radon({sup 222}Rn) gas is the natural radiation generated by radioactive decay of uranium({sup 238}U) nuclide. The radon which exists in ground flows into the inside by the atmospheric temperature, the differential-pressure or a gap of building underground and a ejection by a drywall with a phosphoric In Korea, Korean Institute of Nuclear Safety had been studied about the inside-radon radioactivity investigation over the nation. In the area around the nuclear power plant, it is possible to exist both of a radioactivity nuclide and a natural. Therefore it is necessary to investigate the radon radioactivity in surrounding area of nuclear power plants. In this study, it is purpose to develop the method of establishing the on-line monitoring system to minimize the radiological effect due to radon gas, based on the real state of radon exposure in Gyeong-ju surrounding Nuclear Power Plant

Development of transmutation technologies of radioactive waste by actinoid hydride

International Nuclear Information System (INIS)

Konashi, Kenji; Matsui, Hideki; Yamawaki, Michio

2001-01-01

Two waste treatment methods, geological disposal and transmutation, have been studied. The transmutation method changes long-lived radioactive nuclides to short-lived one or stabilizes them by nuclear transformation. The transmutation by actinoid hydride is exactly alike that transformation method from actinoid disposal waste to Pu fuel. For this object, OMEGA project is processing now. The transmutation is difficult by two causes such as large amount of long-lived radioactive nuclides and not enough development of control technologies of nuclear reaction except atomic reactor. The transmutation using actinoid hydride has merits that the amount of actinoid charged in the target increases and the effect of thermal neutrons on fuel decreases depending on homogeneous transmutation velocity in the target. Development of stable actinoid hydride under the conditions of reactor temperature and irradiation environment is important. The experimental results of U-ZrH 1.6 are shown in this paper. The irradiation experiment using Th hydride has been proceeding. (S.Y.)

Radioactive waste generated from JAERI partitioning-transmutation cycle system

Energy Technology Data Exchange (ETDEWEB)

Shinichi, Nakayama; Yasuji, Morita; Kenji, Nishihara [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan)

2001-07-01

Production of lower-level radioactive wastes, as well as the reduction in radioactivity of HLW, is an important performance indicator in assessing the viability of a partitioning-transmutation system. We have begun to identify the chemical compositions and to quantify the amounts of radioactive wastes that may be generated by JAERI processes. Long-lived radionuclides such as {sup 14}C and {sup 59}Ni and spallation products of Pb-Bi coolants are added to the existing inventory of these nuclides that are generated in the current fuel cycle. Spent salts of KCl-LiCl, which is not generated from the current fuel cycle, will be introduced as a waste. (author)

Radioactive Wastes Generated From JAERI Partitioning-Transmutation Fuel Cycle

International Nuclear Information System (INIS)

Nakayama, Shinichi; Morita, Yasuji; Nishihara, Kenji

2003-01-01

Production of lower-level radioactive wastes, as well as the reduction in radioactivity of HLW, is an important performance indicator in assessing the viability of a partitioning-transmutation system. We have begun to identify the chemical compositions and to quantify the amounts of radioactive wastes that may be generated by JAERI's processes. Long-lived radionuclides such as 14 C and 59 Ni and spallation products of Pb-Bi coolants are added to the existing inventory of these nuclides that are generated in the current fuel cycle. Spent salts of KCl-LiCl, which is not generated from the current fuel cycle, will be introduced as a waste. (authors)

Development of high-level radioactive waste treatment and conversion technologies 'Dry decontamination technology development for highly radioactive contaminants'

Energy Technology Data Exchange (ETDEWEB)

Oh, Won Zin; Lee, K. W.; Won, H. J.; Jung, C. J.; Choi, W. K.; Kim, G. N.; Moon, J. K

2001-04-01

The followings were studied through the project entitled 'Dry Decontamination Technology Development for Highly Radioactive Contaminants'. 1.Contaminant Characteristics Analysis of Domestic Nuclear Fuel Cycle Projects(NFCP) and Applicability Study of the Unit Dry-Decontamination Techniques A. Classification of contaminated equipments and characteristics analysis of contaminants B. Applicability study of the unit dry-decontamination techniques 2.Performance Evaluation of Unit Dry Decontamination Technique A. PFC decontamination technique B. CO2 decontamination technique C. Plasma decontamination technique 3.Development of Residual Radiation Assessment Methodology for High Radioactive Facility Decontamination A. Development of radioactive nuclide diffusion model on highly radioactive facility structure B. Obtainment of the procedure for assessment of residual radiation dose 4.Establishment of the Design Concept of Dry Decontamination Process Equipment Applicable to Highly Radioactive Contaminants 5.TRIGA soil unit decontamination technology development A. Development of soil washing and flushing technologies B. Development of electrokinetic soil decontamination technology.

[Nationwide survey on radioactive waste management related to positron emission tomography in Japan].

Science.gov (United States)

Nagaoka, Hiroaki; Watanabe, Hiroshi; Yamaguchi, Ichiro; Fujibuchi, Toshioh; Kida, Tetsuo; Tanaka, Shinji

2009-12-20

A clearance system for medical radioactive solid waste has not yet been implemented in Japan. Since 2004 new regulations have allowed institutions using positron emission tomography(PET)to handle totally decayed radioactive waste as non-radioactive waste after decay-in-storage. It was expected that this new regulation would mediate the installation of clearance systems in Japan. In order to assess the current situation of radiation safety management in PET institutions, we conducted a nationwide survey. The study design was a cross-sectional descriptive study conducted by questionnaire. The subjects of this survey were all the PET institutions in Japan. Among 224 institutes, 128 institutes are equipped with cyclotrons and 96 institutes are not. The number of returned questionnaires was 138. Among institutes that are using delivered radiopharmaceuticals, 80% treat their waste as non-radioactive according to the new regulation. The impact of new regulations for reducing radioactive waste in PET institutes without a cyclotron was estimated at about $400 thousand per year. The main concern of medical institutes was assessment of the contamination caused by by-products of radioactive nuclides generated in target water during the operation of a cyclotron. It was thought that a rational rule based on scientific risk management should be established because these by-products of radioactive nuclides are negligible for radiation safety. New regulation has had a good influence on medical PET institutes, and it is expected that a clearance system for medical radioactive waste will be introduced in the near future, following these recent experiences in PET institutes.

Investigation of radioactive contamination at non-radioactive drains of the Tsuruga Nuclear Power Station

International Nuclear Information System (INIS)

Koide, Hiroaki; Imanaka, Tetsuji; Ebisawa, Toru; Kawano, Shinji; Kobayashi, Keiji.

1982-05-01

In April, 1981, it was disclosed that a drainage area at the Tsuruga Nuclear Power Station was so much contaminated with radioactivites. Although Ministry of International Trade and Industry (MITI) officially provided an explanation of a process that resulted in the contamination, many problems remain unsolved on account of insufficient and limited investigations. The authors collected mud samples from contaminated manholes and examined radioactivities in them through the measurement of #betta#- and #betta#-spectra. Chemical separation of the samples was carried out in order to obtain precise concentration of radioactive cesium. Results are as follows: i) the concentration of radioactivities does not show monotonous decrease along the stream line but an anomalous peak at downstream manholes, ii) at the manhole specified No. 6 located rather downstream, 137 Cs concentration is significantly high and the composition of radioactive nuclides is quite different from that in the other manholes, and iii) additional radioactive contamination was observed in other manholes of non-radioactive drains which would not be influenced by the accident explained by MITI. Our present work has provided much more data than by MITI and made it clear that the overall data cnnot be consistent with the simple MITI explanation; a single radioactive release accident caused the disclosed contamination. It is concluded that non-radioactive water drains at the Tsuruga Nuclear Power Station had been under continual contamination. (author)

Studies on radioactivities of dust samples in the air at high altitudes

International Nuclear Information System (INIS)

Kohara, Eri; Muronoi, Naohiro

2015-01-01

The radioactivity concentrations of airborne dust samples were studied. The samples had been collected at high altitude by the Japan Air Self-Defense Force from April 2013 to March 2014. The obtained data were used for gross beta radioactivity analysis and gamma nuclide analysis. It is shown that cesium 137 was mainly detected at the 10 km and 3 km altitude of central area of Japan in several samples. Gaseous radioiodine was not detected in all the samples. Radioactive xenon was detected but the concentration did not show significant difference to the background level. (author)

Development of Radioactive Substance Contamination Diffusion Preventive Equipment for a Hot cell

International Nuclear Information System (INIS)

Choo, Yong Sun; Kim, Do Sik; Baik, Seung Je; Yoo, Byung Ok; Kim, Ki Ha; Lee, Eun Pyo; Ahn, Sang Bok; Ryu, Woo Seok

2009-01-01

The hot cell of irradiated materials examination facility (IMEF), which has been operating since 1996, is generally contaminated by the radioactive nuclides of irradiated nuclear fuels and structural steels like Cs-137, Co-60, Co-134 and Ru-106. Especially Cs-137 is a main contaminated radioactive isotope which is easily moved here and there due to air flow in the hot cell, water-soluble, extremely toxic, and has a half-life of 30.23 years. To repair or fix the abnormal function of test apparatus installed in the hot cell, the maintenance door, so called a rear door and located at an intervention area, is opened to enter the hot cell inside. In a moment of opening the maintenance door, dirty air diffusion from the hot cell to an intervention area could be occurred in spite of increasing the rpm of exhaust fan to maintain much low under pressure, but an adjacent area to a maintenance door, i.e. intervention area, is very severely contaminated due to the unpredictable air flow. In this paper, the development of the radioactive substance contamination diffusion preventive equipment for a hot cell is studied to prevent dirty and toxic gaseous radioactive nuclides diffusion from a hot cell and installed at an intervention area of IMEF

Special actinide nuclides: Fuel or waste?

International Nuclear Information System (INIS)

Srinivasan, M.; Rao, K.S.; Dingankar, M.V.

1989-01-01

The special actinide nuclides such as Np, Cm, etc. which are produced as byproducts during the operation of fission reactors are presently looked upon as 'nuclear waste' and are proposed to be disposed of as part of high level waste in deep geological repositories. The potential hazard posed to future generations over periods of thousands of years by these long lived nuclides has been a persistent source of concern to critics of nuclear power. However, the authors have recently shown that each and every one of the special actinide nuclides is a better nuclear fuel than the isotopes of plutonium. This finding suggests that one does not have to resort to exotic neutron sources for transmuting/incinerating them as proposed by some researchers. Recovery of the special actinide elements from the waste stream and recycling them back into conventional fission reactors would eliminate one of the stigmas attached to nuclear energy

A methodological approach to a realistic evaluation of skin absorbed doses during manipulation of radioactive sources by means of GAMOS Monte Carlo simulations

Science.gov (United States)

Italiano, Antonio; Amato, Ernesto; Auditore, Lucrezia; Baldari, Sergio

2018-05-01

The accurate evaluation of the radiation burden associated with radiation absorbed doses to the skin of the extremities during the manipulation of radioactive sources is a critical issue in operational radiological protection, deserving the most accurate calculation approaches available. Monte Carlo simulation of the radiation transport and interaction is the gold standard for the calculation of dose distributions in complex geometries and in presence of extended spectra of multi-radiation sources. We propose the use of Monte Carlo simulations in GAMOS, in order to accurately estimate the dose to the extremities during manipulation of radioactive sources. We report the results of these simulations for 90Y, 131I, 18F and 111In nuclides in water solutions enclosed in glass or plastic receptacles, such as vials or syringes. Skin equivalent doses at 70 μm of depth and dose-depth profiles are reported for different configurations, highlighting the importance of adopting a realistic geometrical configuration in order to get accurate dosimetric estimations. Due to the easiness of implementation of GAMOS simulations, case-specific geometries and nuclides can be adopted and results can be obtained in less than about ten minutes of computation time with a common workstation.

Influence of nuclear reactor accident at Chernobyl' on the environmental radioactivity in Toyama

International Nuclear Information System (INIS)

Morita, Miyuki; Shoji, Miki; Honda, Takashi; Sakanoue, Masanobu.

1987-01-01

The environmental radioactivity caused by the reactor accident at Chernobyl' was investigated from May 7 to May 31 of 1986 in Toyama. Measurement of radioactivities in airborne particles, rain water, drinking water, milk, and mugwort are carried out by gamma-ray spectrometry (pure Ge detector; ORTEC GMX-23195). Ten different nuclides ( 103 Ru, 106 Ru, 131 I, 132 Te-I, 134 Cs, 136 Cs, 137 Cs, 140 Ba-La) are identified from samples of airborne particles. In the air samples, a maximum radioactivity concentration of each nuclide is observed on 13th May 1986. The time of the reactor shut-down and the flux of thermal neutron at the reactor were calculated from 131 I/ 132 I and 137 Cs/ 134 Cs ratio. The exposure dose in Toyama by this accident is given as follows: internal exposure; [thyroid] adult-59 μSv, child-140 μSv, baby-130 μSv, [total body] adult-0.2 μSv, child, baby-0.4 μSv, external exposure; 7 μSv, effective dose equivalent; adult-9 μSv, child-12 Sv, baby-11 μSv. (author)

Monitoring of radioactivity in the environs of Finnish nuclear power stations in 1986

International Nuclear Information System (INIS)

Ilus, E.; Sjoeblom, K.L.; Aaltonen, H.; Klemola, S.; Arvela, H.

1987-06-01

Results of the environmental programmes monitoring radioactivity around the Finnish nuclear power stations in 1986 are reported. After the end of April the fallout nuclides from the Chernobyl accident predominated in all samples taken from the environs of the two power stations Loviisa and Olkiluoto. Radionuclides originating from the Finnish power stations were detected mainly in samples taken from the aquatic environment. The concentrations of the locally discharged nuclides were very low in comparison with the fallout nuclides and their impact on the radiation doses of the population was insignificant. Both nuclear power stations are situated in the main fallout area in Finland. The results of these large monitoring programmes give a good picture of the behaviour of the Chernobyl fallout in the specific areas in Finland

Nuclide creation and annealing reactor waste in neutron fields

International Nuclear Information System (INIS)

Kondrat'ev, V.N.; Kadenko, I.M.

2007-01-01

We consider chemical elements in the Universe (their properties and transmutations) as a fuel powering an evolution of stars, galaxies, etc. The nuclear fusion reactions represent an energy source of stars and, in particular, the Sun fitting the life on the Earth. This brings a question on an origin and conditions for creation of life. We discuss some specific features of nuclear reaction chains at the hydrostatic burning of nuclides in stars and treaties for development of thermonuclear fusion reactors at the Earth based environment. The nova and supernova give promising astrophysical site candidates for synthesis of heavy atomic nuclei and renewing other nuclear components. Such an explosive nucleosynthesis yields the actinides containing basic fuel for nuclear fission reactors, among others. We briefly outline the e-, s-, and r-processes while accounting for ultra-strong stellar magnetization, and discuss some ideas for annealing the radioactive toxic nuclear waste

Methods and apparatus for determining the spatial distribution of a radioactive material

International Nuclear Information System (INIS)

Todd, R.W.

1975-01-01

The spatial distribution of a radioactive material is determined by locating the positions of and energy losses resulting from Compton interactions which occur in a detector as a result of gamma photons emitted by the radioactive material, which may, for example, have been administered to a patient for medical diagnostic investigation. (auth)

Assessment methodology for radioactive effluents

International Nuclear Information System (INIS)

Anon.

1977-01-01

The objective of this environmental assessment is to define and rank the needs for controlling radioactive effluents from nuclear fuel cycle facilities. The assessment is based on environmental standards and dose-to-man calculations. The study includes three calculations for each isotope from each facility: maximum individual dose for a 50-year dose commitment from a 1-yr exposure according to the organ affected; population dose for a 50-yr dose commitment from a 1-yr exposure according to the organ affected; and annual dose rate for the maximally exposed individual. The relative contribution of a specific nuclide and source to the total dose provides a method of ranking the nuclides, which in turn identifies the sources that should receive the greatest control in the future. These results will be used in subsequent tasks to assess the environmental impact of the total nuclear fuel cycle

Further development of semiconductography for low energy beta nuclides and its application for standard radioactive sources and in chemistry and biology

International Nuclear Information System (INIS)

Tykva, R.

1975-05-01

A method called semiconductography has been developed and applied to determine distribution of radionuclides emitting corpuscular radiation. This method is fully automated and is based on a programmed detection of the distribution of radionuclides by means of a special surface barrier silicon detector. Simultaneously with the record of the distribution of activity the contour of the sample can also be determined. A special technology has been developed for production of semiconductor detectors permitting detection of low-energy electrons at room temperature and under normal pressure. In comparison to the detectors from Ortec, U.S.A. and diffused silicon detectors from General Electric, U.S.A., the detectors developed by investigators under the research contract are superior in performance in determining the distribution of radionuclides including the low-energy beta-nuclides in tracer experiments in the life sciences. Compared to current ionisation, scintillation, spark chamber, and autoradiographic methods, semiconductography exhibits several special features. It has a high energy resolution permitting discrimination between radionuclides of energies close to each other (e.g., 14 C and 35 S) and determination of the volume distribution of radionuclides in a non-destructive manner. The results obtained under the contract show that in various life-sciences (biochemistry, molecular biology, embryology, teratology, botany, pharmacology), semiconductography with radionuclide-labelled compounds can offer better means to solve such problems which are difficult to approach by usual isotopic methods. The semiconductography has also been successfully used in the determination of non-homogeneity of planar reference sources and in production of labelled substances

Environmental radioactivity at the National Nuclear Research Centre, Pelindaba

International Nuclear Information System (INIS)

Brits, R.J.N; Prinsloo, L.; De Jesus, A.S.M.

1981-07-01

The revised environmental survey program, introduced during 1970 with the emphasis on monitoring of the critical paths of exposure of the general public, was continued in 1980. Results of determinations of both gross radioactivity and individual nuclides in samples of fish and water (which are critical materials for liquid-effluent releases) from the Hartbeespoort Dam and from the Crocodile River, are given and discussed. Results of 131 I, 0 Sr and gamma-spectrometric analyses of milk, the critical material for releases to the atmosphere, are presented. Results are given of regular investigations of the composition of airborne releases to the atmosphere and liquid-effluent releases to the Crocodile River, performed in order to detect other possible critical nuclides. Levels of deposited and airborn activity from nuclear-bomb tests are reported. Due to the absence of fresh fallout, the levels for most fission products have fallen below the limit of detection. No environmental radioactivity resulting from NNRC releases could be detected above the natural background or accumulated fallout levels [af

Natural radioactivity levels in lake sediment samples

International Nuclear Information System (INIS)

Eroglu, H.; Kabadayi, O.

2013-01-01

The radioactivity concentrations of nuclides 238 U, 232 Th and 40 K in lake sediments collected from 15 different stations at Altinkaya dam lake and 12 different stations at Derbent dam lake in Turkey were measured using high-resolution gamma-ray spectrometry. The measurement was done using a coaxial HPGe detector system coupled to the Ortec-Dspect jr digital MCA system. The average measured activity concentrations of the nuclides 238 U, 232 Th and 40 K were found to be 19.5, 27.7 and 460 Bq kg -1 in Altinkaya dam, whereas the activity concentrations were 18.8, 25.5 and 365 Bq kg -1 in Derbent dam, respectively. The measured activity concentrations in the present study have been compared with similar measurements from different locations in the world. (authors)

Gamma-spectrometric and total alpha-beta counting methods for radioactivity analysis of deuterium depleted water

International Nuclear Information System (INIS)

Ferdes, Ov. S.; Mladin, C.; Vladu, Mihaela; Bulubasa, G.; Bidica, N.

2008-01-01

According to national regulations, as well as to the EU directive on the quality of drinking water, the radionuclide concentrations represent some of the drinking water quality parameters. Among the most important radioactivity content parameters are: the total alpha and total beta concentration (Bq/l); K-40 content, and the gamma-nuclides volume activities. The paper presents the measuring methods for low-level total alpha and/or beta counting of volume samples, as well as the high-resolution gamma-ray spectrometric method used to measure the volume activity of nuclides in drinking water. These methods are applied to monitor the radioactivity content and quality of the QLARIVIA brand of Deuterium depleted water (DDW). There are discussed the performances of these applied methods as well as some preliminary results. (authors)

Analytical method for solving radioactive transformations

International Nuclear Information System (INIS)

Vukadin, Z.

1999-01-01

The exact method of solving radioactive transformations is presented. Nonsingular Bateman coefficients, which can be computed using recurrence formulas, greatly reduce computational time and eliminate singularities that often arise in problems involving nuclide transmutations. Depletion function power series expansion enables high accuracy of the performed calculations, specially in a case of a decay constants with closely spaced values. Generality and simplicity of the method make the method useful for many practical applications. (author)

Nuclide Importance and the Steady-State Burnup Equation

International Nuclear Information System (INIS)

Sekimoto, Hiroshi; Nemoto, Atsushi

2000-01-01

Conventional methods for evaluating some characteristic values of nuclides relating to burnup in a given neutron spectrum are reviewed in a mathematically systematic way, and a new method based on the importance theory is proposed. In this method, these characteristic values of a nuclide are equivalent to the importances of the nuclide. By solving the equation adjoint to the steady-state burnup equation with a properly chosen source term, the importances for all nuclides are obtained simultaneously.The fission number importance, net neutron importance, fission neutron importance, and absorbed neutron importance are evaluated and discussed. The net neutron importance is a measure directly estimating neutron economy, and it can be evaluated simply by calculating the fission neutron importance minus the absorbed neutron importance, where only the absorbed neutron importance depends on the fission product. The fission neutron importance and absorbed neutron importance are analyzed separately, and detailed discussions of the fission product effects are given for the absorbed neutron importance

Radioactivity on the experimental notebook of Mme. Curie. Collection of Meisei University Library

International Nuclear Information System (INIS)

Mori, Chizuo; Inoue, Kazumasa; Chiwa, Kiyoshi; Miyahara, Junji

2005-01-01

The contamination with radioactive material of the notebook written by Marie Curie, collected in the library of Meisei University, Tokyo, was studied by use of Imaging Plate to obtain the distribution images of the contamination on the front and back covers, Si detector to obtain the energy spectrum of α-particles from the cover, and HPGe detector to obtain γ-ray spectrum. The distribution images showed that the contamination appeared mainly at the area held with hands, and even the end of the notebook was contaminated. Many dots of the contamination might imply that there were powdery contaminations around her circumstances. Energy spectra of α-particles and γ-rays showed that most of the nuclei were 226 Ra and the daughters. The radioactivity level at the intensely contaminated part was just below the permissible level, 4 Bq/cm 2 , of surface contamination for α-nuclides of Japan. Number of pages written in every month over 15 years was examined for the purpose to imagine the circumstances at that time, and some remarks were given by referring her biographies which include a matter on a Japanese researcher. (author)

The ENSDF radioactivity data base for IBM-PC and computer network access

International Nuclear Information System (INIS)

Ekstroem, P.; Spanier, L.

1989-08-01

A database for about 15000 gamma rays from 2777 radioactive nuclides derived from the international Evaluated Nuclear Structure Data File (ENSDF) is described together with supporting computer codes. The database is available on a PC diskette, costfree, from the IAEA Nuclear Data Section. (author)

Halftone display, particularly for a high resolution radioactivity distribution detection system

International Nuclear Information System (INIS)

Grenier, R.P.

1977-01-01

A device is described for presenting a halftone pictorial presentation composed of dot picture elements by selectively controlling the number of dot picture elements per unit area at locations on a display. In a high resolution radioactivity distribution detection system, the number of detected radioactive elements at XY locations of an array of sensing devices are fed to a computer and stored at corresponding address locations. The number of radioactive events detected at each address location is normalized into Gray scale coded signals as a function of the greatest number of radioactive events detected at any one address location. The normalized Gray scale coded signals are applied to a display for controlling the number of dot picture elements per unit area presented at corresponding XY locations on the display. The number of radioactive events detected at XY locations of the array are presented on the display as a halftone pictorial representation; the greatest number of picture dot elements per unit are being presented as a brighter image

Microdosimetric implications of the nonuniformity of deposition patterns of inhaled radioactive nuclides

International Nuclear Information System (INIS)

Balashazy, I.; Palfalvi, J.; Hofmann, W.

2000-01-01

local inhomogeneities for all particle sizes and flow rates considered here (except for nanometer-sized particles at very low flow rates). The maximum values of the enhancement factors in a bifurcation strongly increased with decreasing patch size, thus illustrating the high degree of inhomogeneities of the deposition patterns in upper human airways. The computed maximum enhancement factors were as high as several hundreds, suggesting that epithelial cells located at these sites will receive massive doses relative to the assumption of a uniform nuclide distribution. Since the prevalent philosophy of inhalation risk assessment is based upon the assumption of a uniform particle deposition pattern, the incorporation of deposition enhancement factors within airway bifurcations will provide more realistic estimates of radiation doses and resulting carcinogenic risk. Such microdosimetric considerations are particularly important for inhaled alpha-emitting radionuclides, such as the short-lived radon progeny, where cellular doses are strongly correlated with the emission sites of alpha particles. (author)

Distribution of radioactivity in the mouse organism after administration of 35S-chondroitin sulphate

International Nuclear Information System (INIS)

Konador, A.; Kawiak, J.

1976-01-01

The follow-up of chondroitin sulphate (ChS) distribution in the organism after its administration by various routes is interesting in view of the possibility of clinical applications. Mice received intraperitoneally and intragastrically 35 S-ChS and the distribution of radioactivity was followed in 10 chosen organs. The dynamics of changes in radioactivity were found to differ in dependence on the type of organ and route of administration. (author)

Engineering materials for high level radioactive waste repository

International Nuclear Information System (INIS)

Wen Zhijian

2009-01-01

Radioactive wastes can arise from a wide range of human activities and have different physical and chemical forms with various radioactivity. The high level radioactive wastes (HLW)are characterized by nuclides of very high initial radioactivity, large thermal emissivity and the long life-term. The HLW disposal is highly concerned by the scientists and the public in the world. At present, the deep geological disposal is regarded as the most reasonable and effective way to safely dispose high-level radioactive wastes in the world. The conceptual model of HLW geological disposal in China is based on a multi-barrier system that combines an isolating geological environment with an engineering barrier system(EBS). The engineering materials in EBS include the vitrified HLW, canister, overpack, buffer materials and backfill materials. Referring to progress in the world, this paper presents the function, the requirement for material selection and design, and main scientific projects of R and D of engineering materials in HLW repository. (authors)

Improvement of WWW chart of the nuclides interface

International Nuclear Information System (INIS)

Okamoto, Tsutomu; Minato, Futoshi; Iwamoto, Osamu; Koura, Hiroyuki

2016-03-01

The booklet 'chart of the nuclides' is issued every 4 years since 1976 from Nuclear Data Center, Japan Atomic Energy Agency. The chart of the nuclides for WWW (World Wide Web) was developed in 1999 in order to be available from the Internet browser. The Internet connection speeds, browser functions and JavaScript libraries has, however, progressed at present compared with the Internet technology in those days. In connection with the release of the 2014 edition of the chart of the nuclides, the interface of the WWW chart of the nuclides has been improved by introducing new Internet technologies aiming at enhancing convenience on accessibilities via browsers. We introduced a scrolling screen that would make capabilities of easy screen movement on a map with the addition of the drag scrolling function. Considering smart phone access, the light-weight edition which introduced automatic switch was prepared. The new system results in reduction in access time and usefulness in mobile environment. The method of making figures of the chart was reconsidered due to addition of new decay schemes to the 2014 edition. SVG (Scalable Vector Graphics) was adopted so as to make figures easily. It is concluded that the accessibilities of WWW chart of the nuclides are substantially improved from the previous version by introducing the new technologies. (author)

Evaluation of induced radioactivity in 10 MeV-electron irradiated spices, (1)

International Nuclear Information System (INIS)

Furuta, Masakazu; Katayama, Tadashi; Ito, Norio; Mizohata, Akira; Matsunami, Tadao; Shibata, Setsuko; Toratani, Hirokazu; Takeda, Atsuhiko.

1994-01-01

Black pepper, white pepper, red pepper, ginger and turmeric were irradiated with 10 MeV electrons from a linear accelerator to a dose of 100 kGy and radioactivity was measured in order to estimate induced radioactivity in the irradiated foods. Induced radioactivity could not be detected significantly by γ-ray spectrometry in the irradiated samples except for spiked samples which contain some photonuclear target nuclides in the list of photonuclear reactions which could produce radioactivity below 10 MeV. From the amount of observed radioactivities of short-lived photonuclear products in the spiked samples and calculation of H 50 according to ICRP Publication 30, it was concluded that the induced radioactivity and its biological effects in the 10 MeV electron-irradiated natural samples were negligible in comparison with natural radioactivity from 40 K contained in the samples. (author)

Study of waterproof capabilities of the engineered barrier containing bentonite in near surface radioactive waste repositories

International Nuclear Information System (INIS)

Luu Cao Nguyen; Nguyen Ba Tien; Doan Thi Thu Hien; Nguyen Van Chinh; Vuong Huu Anh

2017-01-01

In Vietnam, the study of nuclear fuel cycle is in first steps, such as the exploitation and uranium processing. These processes generated large amounts of radioactive waste over-timing. The naturally occurring radioactive material and technologically enhanced radioactive material (NORM/TENORM) waste, which would be large, needs to be managed and disposed reasonably by effective methods. These wastes were used to be disposal in the near surface. It was therefore very important to study the model of radioactive waste repository, where bentonite waterproofing layer would be applied for the engineered barrier. The aim of this study was to obtain the preliminary parameters for low-level radioactive waste disposal site being suitable with the conditions of Vietnam. The investigation of the ratio between soil and bentonite was taken part. The experiments with some layers of waterproofing material with the ratio of soil and bentonite as 75/25, 50/50 and 25/75 were carried out to test the moving of uranium nuclide through these waterproofing material layers. Analyzing the uranium content in each layer (0.1 cm) of pressed soil - bentonite mixture (as a block) to determine the uranium nuclide adsorption from solution into the materials in the different ratios at the different times: 1, 2 and 3 months was carried out. The results showed that the calculated average rate of uranium nuclide migration into the soil - bentonite layer was 5.4x10 -10 , 5.4x10 -10 and 3.85x10 -10 m/s corresponding to the waterproofing layer thickness (for 300 years) 4.86 m, 4.86 m and 3.63 m respectively, which was due on the ratio of soil and bentonite 75/25, 50/50, 25/75 to keep the safety for the repository. (author)

Experimental study on treatment of simulated boron containing radioactive wastewater by reverse osmosis membrane

International Nuclear Information System (INIS)

Wang Xiaowei; Yang Kai; Kong Jinsong

2012-01-01

Experiments were carried out on a pilot equipment to study the performance of treatment of simulated boron containing radioactive wastewater by reverse osmosis membrane. Results showed that the rejection efficiency of boron, simulated nuclides and salts in simulated wastewater could be enhanced by increasing the feedwater pH, improving the applied pressure or reducing the recovery ratio. By adjusting the simulated wastewater pH to 9.0, the boron concentration in permeate could be lower than 5 mg/L and two nuclides including cobalt and cesium could be removed to a satisfied extend. (authors)

The study on radioactivity reduction of spent PWR cladding hull

International Nuclear Information System (INIS)

Jung, I. H.; Kim, J. H.; Park, C. J.; Jung, Y. H.; Song, K. C.; Lee, J. W.; Park, J. J.; Yang, M. S.

2003-01-01

Hull arising from the spent PWR fuel elements is classified as a high-level radioactive waste. This report describes the radio-chemical characteristics of the hull-from PWR spent fuel of 32,000MWd/tU burn-up and 15 years cooling, discharged from Gori Unit I cycled 4-7-by examination and literature survey. On the basis of the results, a method of degradation to middle and low-level radioactive waste was proposed by dry process such as laser or plasma technique with removing the nuclides deposited on the surface of the hull

Development of prototype liquid scintillator system for monitoring liquid radioactive waste

International Nuclear Information System (INIS)

Nam, Uk Won; Seon, Kwang Il; Kong, Kyoung Nam; Kim, Chang Kyu; Lee, Dong Myung; Lee, Sang Kook

2003-01-01

A prototype liquid scillatillator system for measurement of multiple beta-labeled mixtures was developed and its characteristic was investigated. The signal processing system consists of two photomultiplier tubes and the coincident count circuit. The characteristic of the system was analyzed using 4 beta-labeled samples ( 3 H, 14 C, 36 Cl and 90 Sr). Beta spectra from the samples were obtained without radiation shielding, and the detection limits for each nuclides were estimated based on the spectra. The estimated detection limits were compared to the legal regulation values. It is found that the liquid radioactive nuclides are detectable well below the legal regulation values

Radioactivity measurements in the vicinity of the mine waste heap at Crossen and radiation dose assessment

International Nuclear Information System (INIS)

Kulzer, R.

1998-01-01

The radiation dose to the population living in the vicinity of the mine waste heap is assessed. The measurements carried out were to verify the dose relevance of ambient radioactivity on site, in particular the ingestion and inhalation pathways and the external exposure pathways. The nuclide Pb-210 was used as an indicator because of its large dose factor for assessment of ingestion and its airborne dispersion as an Rn-222 daughter product. The waste heap material releases large quantities of this nuclide. Ingestion of radioactivity from the waste heap may be caused by wind-borne erosion and activity deposition on plants in the area. Therefore, the specific activities of Pb-210 and Ra-226 have been measured in soil and plant specimens sampled at various distances from the waste heap. (orig./CB) [de

New approach to neutron-induced transmutation, radioactivity and afterheat calculations and its application to fusion reactors

International Nuclear Information System (INIS)

Fukumoto, Hideshi

1986-01-01

A new method and an accompanying computer code CINAC have been developed for the calculation of neutron-induced transmutation, radioactivity and afterheat. In the method, the generation and depletion of nuclides during and after reactor operation are described in a matrix form in which the arrangement of nuclides is determined systematically. The solutions are obtained by an eigenvalue analysis of the matrix without any time steps or iterative schemes which would increase the computational time. The method can treat any type of activation chains equally, and it gives analytical solutions for linear chains. The CINAC code, coupled with the radiation transport codes ANISN and DOT3.5, can also calculate the dose distribution at any time after shutdown in a one- or two-dimensional geometry of fusion reactors. Two calculations were carried out using CINAC to confirm its validity. The results were compared to those calculated by the THIDA code system which is based on a matrix exponential method. The new method was 50 times faster than the latter, while the discrepancy between them was 4 % at the most. (author)

Uncertainties in the production of p nuclides in thermonuclear supernovae determined by Monte Carlo variations

Science.gov (United States)

Nishimura, N.; Rauscher, T.; Hirschi, R.; Murphy, A. St J.; Cescutti, G.; Travaglio, C.

2018-03-01

Thermonuclear supernovae originating from the explosion of a white dwarf accreting mass from a companion star have been suggested as a site for the production of p nuclides. Such nuclei are produced during the explosion, in layers enriched with seed nuclei coming from prior strong s processing. These seeds are transformed into proton-richer isotopes mainly by photodisintegration reactions. Several thousand trajectories from a 2D explosion model were used in a Monte Carlo approach. Temperature-dependent uncertainties were assigned individually to thousands of rates varied simultaneously in post-processing in an extended nuclear reaction network. The uncertainties in the final nuclear abundances originating from uncertainties in the astrophysical reaction rates were determined. In addition to the 35 classical p nuclides, abundance uncertainties were also determined for the radioactive nuclides 92Nb, 97, 98Tc, 146Sm, and for the abundance ratios Y(92Mo)/Y(94Mo), Y(92Nb)/Y(92Mo), Y(97Tc)/Y(98Ru), Y(98Tc)/Y(98Ru), and Y(146Sm)/Y(144Sm), important for Galactic Chemical Evolution studies. Uncertainties found were generally lower than a factor of 2, although most nucleosynthesis flows mainly involve predicted rates with larger uncertainties. The main contribution to the total uncertainties comes from a group of trajectories with high peak density originating from the interior of the exploding white dwarf. The distinction between low-density and high-density trajectories allows more general conclusions to be drawn, also applicable to other simulations of white dwarf explosions.

Technical factors in the site selection for a radioactive wastes storage of low and intermediate level

International Nuclear Information System (INIS)

Badillo A, V. E.; Ramirez S, J. R.; Palacios H, J. C.

2009-10-01

The storage on surface or near surface it is viable for wastes of low and intermediate level which contain radio nuclides of short half life that would decay at insignificant levels of radioactivity in some decades and also radio nuclides of long half life but in very low concentrations. The sites selection, for the construction of radioactive waste storages, that present an appropriate stability at long term, a foreseeable behavior to future and a capacity to fulfill other operational requirements, is one of the great tasks that confront the waste disposal agencies. In the selection of potential sites for the construction of a radioactive wastes storage of low and intermediate level, several basic judgments should be satisfied that concern to physiography, climatology, geologic, geo-hydrology, tectonic and seismic aspects; as well as factors like the population density, socioeconomic develops and existent infrastructure. the necessary technician-scientific investigations for the selection of a site for the construction of radioactive waste storages are presented in this work and they are compared with the pre-selection factors realized in specify areas in previous studies in different regions of the Mexican Republic. (Author)

Radiation protection and ambient radioactivity monitoring in the area of the Asse mine. Annual report 1997

International Nuclear Information System (INIS)

Meyer, H.; Stippler, R.

1998-01-01

The number of annual sampling and measurements performed in compliance with the operator's monitoring duties have been the same as last year: 364. All measured radioactivity values were at the level of natural environmental radioactivity. Some samples and measurements reflected the fallout from former atmospheric nuclear weapons tests and the accident at the Chernobyl reactor. Personnel dosimetry was performed according to legal requirements of the Radiation Protection Ordinance, as were measurements for the monitoring of ambient doses, dose rates and radioactivity levels in the air of the mine structures. All measured values were below the maximum permissible personal doses and occupational dose limits. Ambient air measurements in the salt mine as in the preceding years detected low amounts of the nuclides H 3, C 14, Pb 210, and the short-lived daughter products of Rn 222 and Rn 220. The calculated radioactivity concentrations in the vicinity of the mine, derived from averaged annual effluents, to some part were below the average natural concentrations of the nuclides. The effluent-induced radiation dose at the most affected location was far below the limits set by the Radiation Protection Ordinance. (orig./CB) [de

Monte Carlo modelling and comparison with experiment of the nuclide production in thick stony targets isotropically irradiated with 600 MeV protons

International Nuclear Information System (INIS)

Aylmer, D.; Herzog, G.F.; Kruse, T.H.; Cloth, P.; Filges, D.; Moniot, R.K.; Signer, P.; Wieler, R.; Tuniz, C.

1987-05-01

Depth profiles for the production of stable and radioactive nuclides have been measured for a large variety of target elements in three thick spherical stony targets with radii of 5, 15 and 26 cm isotropically irradiated with 600 MeV protons at the CERN synchrocyclotron. These irradiation experiments (CERN SC96) were intended to simulate the irradiation of meteoroids by galactic cosmic ray protons. In order to combine this experimental approach with a theoretical one the intra- and internuclear cascades were calculated using Monte Carlo techniques via the high energy transport code HET/KFA 1. Together with transport calculations for low energy neutrons by the MORSE-CG code the depth dependent spectra of primary and secondary protons and of secondary neutrons were derived. On the basis of these spectra and a set of evaluated experimental excitation functions for p-induced reactions and of theoretical ones for n-induced reactions, calculated by the code ALICE LIVERMORE 82, theoretical depth profiles for the production of stable and radioactive nuclides in the three thick targets were calculated. This report is a comprehensive survey on all those target/product combination for which both experimental and theoretical data are available. It provides the basis for a detailed discussion of the various production modes of residual nuclides and on the depth and size dependence of their production rates in thick stony targets, serving as a simulation of the galactic cosmic ray irradiation of meteoroids in space. On the other hand the comparison of the experimental and theoretical depth profiles validates the high energy transport calculations, making them a promissing tool for further model calculations of the interactions of cosmic rays with matter. (orig.)

Method of processing radioactive metallic sodium with recycling alcohols

International Nuclear Information System (INIS)

Sakai, Takuhiko; Mitsuzuka, Norimasa.

1980-01-01

Purpose: To employ high safety alcohol procession and decrease the amount of wastes in the procession of radioactive metallic sodium discharged from LMFBR type reactors. Method: Radioactive metallic sodium containing long half-decay period nuclides such as cesium, strontium, barium, cerium, lanthanum or zirconium is dissolved in an alcohol at about 70% purity. After extracting the sodium alcoholate thus formed, gaseous hydrochloride is blown-in to separate the sodium alcoholate into alcohol and sodium chloride, and regenerated alcohol is used again for dissolving sodium metal. The sodium chloride thus separated is processed into solid wastes. (Furukawa, Y.)

Measurements of radioactive dust in high altitude air

International Nuclear Information System (INIS)

Kobayashi, Mika; Kohara, Eri; Muronoi, Naohiro; Masuda, Yousuke; Midou, Tomotaka; Ishida, Yukiko; Shimizu, Toshihiko; Saga, Minoru; Endo, Hiromu

2012-01-01

The radioactivity in samples of airborne dust was measured. The samples had been collected at high altitude by the Japan Air Self-Defense Force. The data were obtained for the gross beta activity, gamma nuclide determination and radiochemical analysis. It was shown that there was no appreciable difference between the activity levels obtained in this time and in the year before. Seasonal variations were not very pronounced. It was found that the radioactivity at high altitude had been stable at a low level. Radioactive gases (gaseous radioiodine and xenon gas) were not detected. This report does not include the result on radionuclide measurements that Technical Research and Development Institute executed for examining the nuclear emergency situation at Fukushima Daiichi and Daini nuclear power plants after Tohoku Region Pacific Ocean Earthquake on March 11, 2011. (author)

Vertical distribution of radioactive particles in Ottawa River sediment near the Chalk River Laboratories

International Nuclear Information System (INIS)

Lee, D.R.; Hartwig, D.S.

2011-01-01

Previously, we described an area of above-background levels of radioactivity in the bed of the Ottawa River near the Chalk River Laboratories. The area was about 200 m wide by 400 m long and in water 8 to 30 m deep. The source of the radioactivity was associated with the location of cooling-water discharge. Particles of radioactive material were later recovered from the upper 10-15 cm of sediment and were determined to be sand-sized grains of nuclear fuel and corrosion products. This report provides an examination of the vertical distribution of radioactive particles in the riverbed. Twenty-three dredge samples (representing 1.2 m 2 of riverbed) were collected near the Process Outfall. Each dredge sample was dissected in horizontal intervals 1-cm-thick. Each interval provided a 524 cm 3 sample of sediment that was carefully examined for particulate radioactivity. Approximately 80% of the radioactivity appeared to be associated with discrete particles. Although the natural sediment in the general area is cohesive, silty clay and contains less than 10% sand, the sediment near the Outfall was found to be rich in natural sand, presumably from sources such as winter sanding of roads at the laboratories. The radioactive particles were almost entirely contained in the top-most 10 cm of the river bed. The majority of the particles were found several centimetres beneath the sediment surface and the numbers of particles and the radioactivity of the particles peaked 3 to 7 cm below the sediment surface. Based on the sediment profile, there appeared to have been a marked decrease in the deposition of particulate radioactivity in recent decades. The vertical distribution of radioactive particles indicated that sedimentation is resulting in burial and that the deposition of most of the particulate radioactivity coincided with the operation of Chalk River's NRX reactor from 1947 to 1992. (author)

Effects of nonequilibrium adsorption on nuclide transport in a porous rock

International Nuclear Information System (INIS)

Shi-Ping Teng; Ching-Hor Lee

1994-01-01

An analytical solution covering the entire range of adsorption properties of rock has been derived for the migration of radionuclide in a porous rock matrix. The analysis takes into account the advective transport, hydrodynamic dispersion, adsorption between solid phase and liquid phase, and the radioactive decay. For adsorption of nuclide within the rock, the effects of no adsorption, linear nonequilibrium adsorption, and linear equilibrium adsorption are integrated into a generic transient analytical solution. The results indicate that the assumption of equilibrium adsorption can result in underestimation of the concentration profile in the early stages of migration. However, both the equilibrium and nonequilibrium profiles eventually approach the same value. It is also noted that for the case of nonequilibrium adsorption, plateaus appear in the concentration profile of the breakthrough curves. The effects of different adsorption rates are also analyzed

Radioactivity in tomatoes grown on mine tailings from Oka, a niobium mining region

International Nuclear Information System (INIS)

Boulet, M.; Boudreau, A.; Roy, J.C.

1983-01-01

The radioactivity contained in the tailings of a niobium mine in the Oka region, Quebec, was the object of concern for the population of the area in 1979. To find the impact of these tailings on fruit and vegetables grown in this environment, an investigation of the radioactivity found on tomatoes grown in green houses in niobium tailings and in vermiculites was undertaken. The tailings contained a high level of natural radioactivity and a small amount of 137 Cs while the vermiculites had a very low level of natural radioactivity and an appreciable amount of 137 Cs. Cesium-137 was the only nuclide detected in tomato ashes in measurable quantity. Absence of natural radioactivity is explained by its presence as insoluble minerals

A study for natural radioactivity levels in some soil samples using gamma spectrometry

International Nuclear Information System (INIS)

Mohamed, Yousif Hassab El Rasoul

1997-05-01

The purpose of this study was to investigate a few selected soil samples and to study their natural radioactivity using gamma spectrometry. The first sample was a rock phosphate from Nuba mountains region which is being considered as a low cost fertilizer. Another sample came from Miri lake area (Nuba mountains) which is known to have elevated natural radioactivity level. The other four samples came from different other regions in Sudan for comparison. The idea was to identify the radioactive nuclides present in these soil samples, to trace their sources and to determine the activity present in them. (Author)

Evaluation of induced radioactivity in 10 MeV electron-irradiated spices

Energy Technology Data Exchange (ETDEWEB)

Furuta, Masakazu; Ito, Norio; Mizohata, Akira; Matsunami, Tadao; Katayama, Tadashi; Toratani, Hirokazu (Osaka Prefectural Univ., Sakai (Japan). Research Inst. for Advanced Science and Technology); Takeda, Atsuhiko

1993-10-01

In order to make clear appreciation to induced radioactivity in the irradiated foods, photonuclear reactions which could produce radioactivity at energies up to 10 MeV were listed up from elemental compositions of black pepper, white pepper, red pepper, ginger and turmeric. The samples were irradiated with 10 MeV electron from a linear accelerator to a dose of 100 kGy and radioactivity was measured. Induced radioactivity could not be detected significantly by gamma-ray spectrometry and beta-ray counting in the irradiated samples except for spiked samples which contain some photonuclear target nuclides in the list. From the amount of observed radioactivities of short-lived photonuclear products in the spiked samples and calculation of H[sub 50] according to ICRP Publication 30, it was concluded that the induced radioactivity and its biological effects in the 10 MeV electron-irradiated natural samples were negligible in comparison with natural radioactivity from [sup 40]K contained in the samples. (J.P.N.).

Role of geochemical factors in the assessment and regulation of geologic disposal of high-level radioactive waste

International Nuclear Information System (INIS)

O'Kelley, G.D.; Meyer, R.E.

1984-03-01

It is generally agreed that in a deep repository for high-level radioactive waste, the agent most likely to mobilize radionuclides and disperse them into the accessible environment is groundwater. Analyses of the performance of a high-level waste repository will require a detailed study of the chemical factors involved in the interaction of water-mobilized nuclides with the host rock. These chemical factors include sorption phenomena, redox processes, the roles of hydrolysis and complexation in the determination of speciation, solubility, and the formation of polymeric and colloidal forms of the nuclides. A discussion and review of these factors is given along with their pertinence to the migration of the nuclides and the development of computer codes for the prediction of this migration. Of particular interest are the formation of negatively charged species of the nuclides, which tend to exhibit very low adsorption, and the formation of insoluble products through redox processes. Knowledge of the different chemical factors must be used to postulate geochemical scenarios for the release of nuclides. Much of the chemistry of the nuclides is very sensitive to pH and redox conditions and, in general, increase of acidity and oxidizing power of the groundwater could have serious consequences with respect to mobilization of the nuclides. 33 references

Compendium of technical computer codes used in support of the DOE Office of Civilian Radioactive Waste Management

International Nuclear Information System (INIS)

McBride, A.F.; Austin, P.N.; Ward, W.M.; McCarn, L.B.; Roddy, J.W.; Ludwig, S.B.; Reich, W.J.; Roussin, R.W.

1989-04-01

A compilation of technical computer codes related to ongoing work under the cognizance of the US Department of Energy's Office of Civilian Radioactive Waste Management (DOE/OCRWM) is presented. Much of the information was obtained from responses to a questionnaire distributed by DOE/OCRWM to all DOE offices associated with the radioactive waste management program. The codes are arranged alphabetically by name. In addition to the code description, each sheet includes other data such as computer hardware and software requirements, document references, name of respondent, and code variants. The codes are categorized into seventeen subject areas plus a miscellaneous category. Some of the subject areas covered are atmospheric dispersion, biosphere transport, geochemistry, nuclear radiation transport, nuclide inventory, and risk assessment. Three appendixes are included which list the names of the contributors, a list of the literature reviewed, and a glossary of computer code terminology and definitions. 50 refs., 3 tabs

Constraining local subglacial bedrock erosion rates with cosmogenic nuclides

Science.gov (United States)

Wirsig, Christian; Ivy-Ochs, Susan; Christl, Marcus; Reitner, Jürgen; Reindl, Martin; Bichler, Mathias; Vockenhuber, Christof; Akcar, Naki; Schlüchter, Christian

2014-05-01

The constant buildup of cosmogenic nuclides, most prominently 10Be, in exposed rock surfaces is routinely employed for dating various landforms such as landslides or glacial moraines. One fundamental assumption is that no cosmogenic nuclides were initially present in the rock, before the event to be dated. In the context of glacially formed landscapes it is commonly assumed that subglacial erosion of at least a few meters of bedrock during the period of ice coverage is sufficient to remove any previously accumulated nuclides, since the production of 10Be ceases at a depth of 2-3 m. Insufficient subglacial erosion leads to overestimation of surface exposure ages. If the time since the retreat of the glacier is known, however, a discordant concentration of cosmogenic nuclides delivers information about the depth of subglacial erosion. Here we present data from proglacial bedrock at two sites in the Alps. Goldbergkees in the Hohe Tauern National Park in Austria and Gruebengletscher in the Grimsel Pass area in Switzerland. Samples were taken inside as well as outside of the glaciers' Little Ice Age extent. Measured nuclide concentrations are analyzed with the help of a MATLAB model simulating periods of exposure or glacial cover of user-definable length and erosion rates.

Data base for site specific migration analysis of radioactive elements in repositories

Energy Technology Data Exchange (ETDEWEB)

Hadermann, J

1982-01-01

Migration analysis is of considerable importance in long-term safety aspects of radioactive waste repositories. The present work gives the data base for a selected part of a comprehensive geosphere transport calculation. We restrict ourselves to a critical evaluation of parameters pertinent to the migration analysis of the /sup 245/Cm chain. This includes the important nuclide /sup 237/Np. With these we are able to perform a site specific calculation for repositories planned in deep geologic formations in Switzerland. It is shown that the granitic basement induces strong time delays in nuclide migration. In contrast to that, the overlaying sedimentary layers cause primarily a dilution of the radionuclide concentrations.

Process and device for determining the spatial distribution of a radioactive substance

International Nuclear Information System (INIS)

1977-01-01

This invention describes a process for determining the spatial distribution of a radioactive substance consisting in determining the positions and energy losses associated to the interactions of the Compton effect and the photoelectric interactions that occur owing to the emission of gamma photons by the radioactive material and in deducing an information on the spatial distribution of the radioactive substance, depending on the positions and energy losses associated to the interactions of the Compton effect of these gamma photons and the positions and energy losses associated to the subsequent photoelectric interactions of these same photons. The invention also concerns a processing system for identifying, among the signals representing the positions and energy losses of the interactions of the Compton effect and the photoelectric interactions of the gamma photons emitted by a radioactive source, those signals that are in keeping with the gamma photons that have been subjected to an initial interaction of the Compton effect and a second and last photoelectric interaction. It further concerns a system for determining, among the identified signals, the positions of the sources of several gamma photons. This detector of Compton interaction can be used with conventional Auger-type imaging system (gamma camera) for detecting photoelectric interactions [fr

Examination of a measuring method for fallout radioactivity released by the accident of the Fukushima Dai-ichi NPS. Surface contamination measurement

International Nuclear Information System (INIS)

Yoshii, Taiki; Kawasaki, Satoru

2013-08-01

Radioactive nuclides were released in the atmosphere by the accident of TEPCO's Fukushima Dai-ichi Nuclear Power Station in March, 2011, and they are detected on the materials that had no artificial radioactive nuclides before the accident. Confronted with this situation, NISA issued a guideline titled 'A guideline regarding treatment of materials in nuclear facilities considering the influence of fallout released from the accident of TEPCO's Fukushima Dai-ichi Nuclear Power Station' on March 30, 2012. Nuclear Regulatory Authority refers to applying the existing bylaw until the time to make decision of the updated bylaw. The guideline shows that after judging whether there is the influence of fallout or not, the conventional clearance and NR systems can be used when there is no influence of fallout. On the other hand, the special treatment is required when it is judged that there is the influence. This report describes a specific example of measuring method to evaluate the influence of fallout, in case of surface contamination. This report focused surface contamination of flat object as target. Preliminary investigation shows that the distribution of surface contamination due to fallout is near to lognormal distribution. Therefore, the sampling measurement can be adopted. The average surface contamination of target is decided from sampling data by using 90% upper confidence limit of Chebyshev inequality. Also, the minimum sampling number is decided. The evaluation of the influence of fallout is judged from the result of surface contamination measurement, weight of target and surface area of target. (author)

The LAW Library -- A multigroup cross-section library for use in radioactive waste analysis calculations

International Nuclear Information System (INIS)

Greene, N.M.; Arwood, J.W.; Wright, R.Q.; Parks, C.V.

1994-08-01

The 238-group LAW Library is a new multigroup neutron cross-section library based on ENDF/B-V data, with five sets of data taken from ENDF/B-VI ( 14 N 7 , 15 N 7 , 16 O 8 , 154Eu 63 , and 155 Eu 63 ). These five nuclides are included because the new evaluations are thought to be superior to those in Version 5. The LAW Library contains data for over 300 materials and will be distributed by the Radiation Shielding Information Center, located at Oak Ridge National Laboratory. It was generated for use in neutronics calculations required in radioactive waste analyses, although it has equal utility in any study requiring multigroup neutron cross sections

Environmental behavior of the radionuclides released from the Fukushima Daiichi Nuclear Power Plant accident

International Nuclear Information System (INIS)

Yamazaki, Hideo

2014-01-01

The environmental behavior of radioactive nuclides released from the Fukushima Daiichi Nuclear Power Station (FDNPS) accident in eastern Japan was investigated. The radioactive pollution of environmental samples, including airborne dust, soil, sediment, fish, and other organisms was described. It was evaluated for environmental behavior and fate of the radioactive material from the spatial and temporal distribution of the radioactive nuclides. In Higashiosaka City about 600 km away from FDNPS, it begins to detect the radioactive nuclides in the airborne dust from 25th March 2011. Radioactive fission products 95 Zr- 95 Nb was detected on 18th April. The concentrations of 131 I, 134 Cs, and 137 Cs in the soil collected from Fukushima City were 126000, 14000, and 14200 Bq/kg on 19th March 2011 and 12800, 13200, and 13700 Bq/kg on 26th March 2011, respectively. The concentrations of 131 I, 134 Cs, and 137 Cs in the soil samples collected from March-June 2011 from study sites in metropolitan area and Kanto region ranged from nd to 91900, 59 to 16100, and 69 to 17600 Bq/kg, respectively. (Concentrations of 131 I were done decay correction to the value of 16th March) Radioactivities in fish samples collected from off FDNPS, Tokyo Bay, and Kejonuma Pond were measured. The radioactive contamination of forest ecosystem was also investigated. Two processes are involved in the radioactive contamination of the environment from the FDNPS accident. One is contamination by radioactive nuclides released from the hydrogen explosion. Leakage of contaminated cooling water to the ocean is in other important environmental pollution. We must continue carefully monitoring of radioactive nuclides in the environment. (author)

Radioactive nuclide production and isomeric state branching ratios in P + W reactions to 200 mev

International Nuclear Information System (INIS)

Young, P.G.; Chadwick, M.B.

1995-01-01

Calculations of nuclide yields from spallation reactions usually assume that the products are formed in their ground states. We are performing calculations of product yields from proton reactions on tungsten isotopes that explicitly account for formation of the residual nuclei in excited states. The Hauser-Feshbach statistical/preequilibrium code GNASH, with full accounting for angular momentum conservation and electromagnetic transitions, is utilized in the calculations. We present preliminary results for isomer branching ratios for proton reactions to 200 MeV for several products including the 31-y, 16+ state in l78 Hf and the 25-d, 25/2- state in 179 Hf. Knowledge of such branching ratios, might be important for concepts such as accelerator production of tritium that utilize intermediate-energy proton reactions on tungsten

Estimating cumulative soil accumulation rates with in situ-produced cosmogenic nuclide depth profiles

International Nuclear Information System (INIS)

Phillips, William M.

2000-01-01

A numerical model relating spatially averaged rates of cumulative soil accumulation and hillslope erosion to cosmogenic nuclide distribution in depth profiles is presented. Model predictions are compared with cosmogenic 21 Ne and AMS radiocarbon data from soils of the Pajarito Plateau, New Mexico. Rates of soil accumulation and hillslope erosion estimated by cosmogenic 21 Ne are significantly lower than rates indicated by radiocarbon and regional soil-geomorphic studies. The low apparent cosmogenic erosion rates are artifacts of high nuclide inheritance in cumulative soil parent material produced from erosion of old soils on hillslopes. In addition, 21 Ne profiles produced under conditions of rapid accumulation (>0.1 cm/a) are difficult to distinguish from bioturbated soil profiles. Modeling indicates that while 10 Be profiles will share this problem, both bioturbation and anomalous inheritance can be identified with measurement of in situ-produced 14 C

Burning Plutonium and minimizing the radioactive waste in existing PWR

International Nuclear Information System (INIS)

Mittag, S.; Kliem, S.

2009-01-01

Long-lived radioactive actinides are produced in light water reactors (LWR) using conventional fuel. 'Innovative' fuel matrices may reduce the breeding of these nuclides. However, inherent LWR safety features have to be preserved, which restricts the possibilities for new fuel-carrying matrices. Respective fuel-assembly and LWR-core safety studies indicate practicable new fuel options for the near future. (authors)

Burning plutonium and minimizing the radioactive waste in existing PWR

International Nuclear Information System (INIS)

Mittag, S.; Kliem, S.

2009-01-01

Long-lived radioactive actinides are produced in light water reactor (LWR) using conventional fuel. 'Innovative' fuel matrices may reduce the breeding of these nuclides. However, inherent LWR safety features have to be preserved, which restricts the possibilities for new fuel-carrying matrices. Respective fuel-assembly and LWR-core safety studies indicate practicable new fuel options for the near future. (Authors)

Nuclides.net: An integrated environment for computations on radionuclides and their radiation

International Nuclear Information System (INIS)

Galy, J.; Magill, J.

2002-01-01

Full text: The Nuclides.net computational package is of direct interest in the fields of environment monitoring and nuclear forensics. The 'integrated environment' is a suite of computer programs ranging from a powerful user-friendly interface, which allows the user to navigate the nuclide chart and explore the properties of nuclides, to various computational modules for decay calculations, dosimetry and shielding calculations, etc. The main emphasis in Nuclides.net is on nuclear science applications, such as health physics, radioprotection and radiochemistry, rather than nuclear data for which excellent sources already exist. In contrast to the CD-based Nuclides 2000 predecessor, Nuclides.net applications run over the internet on a web server. The user interface to these applications is via a web browser. Information submitted by the user is sent to the appropriate applications resident on the web server. The results of the calculations are returned to the user, again via the browser. The product is aimed at both students and professionals for reference data on radionuclides and computations based on this data using the latest internet technology. It is particularly suitable for educational purposes in the nuclear industry, health physics and radiation protection, nuclear and radiochemistry, nuclear physics, astrophysics, etc. The Nuclides.net software suite contains the following modules/features: a) A new user interface to view the nuclide charts (with zoom features). Additional nuclide charts are based on spin, parity, binding energy etc. b) There are five main applications: (1) 'Decay Engine' for decay calculations of numbers, masses, activities, dose rates, etc. of parent and daughters. (2) 'Dosimetry and Shielding' module allows the calculation of dose rates from both unshielded and shielded point sources. A choice of 10 shield materials is available. (3) 'Virtual Nuclides' allows the user to do decay and dosimetry and shielding calculations on mixtures of

Investigation of the environmental radioactivity around the mooring port

International Nuclear Information System (INIS)

Tanigawa, Yoshio

1976-01-01

Here are the main data for radioactivity examination performed in 1975 at Mutsu port, the mooring port of atomic energy vessel ''Mutsu''. No abnormality were observed in space γ ray dose ratio, and integrated doses measured by the thermofluorescence dosimeter at three monitoring posts in the port (G M tube) and three monitoring station in Mutsu City. A serial measurement of radioactivity concentration in sea water did not show any abnormality, either. Samples were taken from the surface soil of the ground, the bottom of the rivers, river water, drinking water, and milk and measured the total radioactivity by a gas flow counter. The measurement of the total β-radioactivity and radio nuclides analysis were carried out in sea water, the soil from the bottom of the sea and sea products. Abnormality considered to be caused by ''Mutsu'' did not observed at all. (Kobatake, H.)

Process for final storage of high level radioactive fission product solution

International Nuclear Information System (INIS)

Ellis, J.R.B.; Fries, B.A.

1984-01-01

In this process for the storage of an aqueous solution of radioactive nuclides, the solution is diluted with system water, which is obtained from a reservoir below the bottom of the sea in a porous geological stratum. After dilution, the diluted solution is injected into the same geological stratum under the bottom of the sea. (orig.) [de

Decontamination of contaminated oils with radio nuclides using magnetic fields

International Nuclear Information System (INIS)

Gutierrez R, C. E.

2011-01-01

The present work is focused in to find a solution to the wastes treatment that are generated during the maintenance to the nuclear power industry, the specify case of the contaminated oils with radio nuclides, for this purpose was necessary to make a meticulous characterization of the oils before the treatment proposal using advanced techniques, being determined the activity of them, as well as their physical-chemical characteristics. By means of the developed procedure that combines the use of magnetic fields and filtration to remove the contaminated material with radioactive particles, is possible to diminish the activity of the oils from values that oscillate between 6,00 and 10,00 up to 0,00 to 0,0003 Bq/ml. The decontamination factor of the process is of 99.00%. The proposal of the necessary technology for to decontaminate the oils is also made and is carried out the economic analysis based on the reuse of these, as well as the calculation of the avoided damages. (Author)

Calibration of nuclides by gamma-gamma sum peak coincidence counting

International Nuclear Information System (INIS)

Guevara, E.A.

1986-01-01

The feasibility of extending sum peak coincidence counting to the direct calibration of gamma-ray emitters having particular decay schemes was investigated, also checkings of the measurement accuracy, by comparing with more precise beta-gamma coincidence counting have been performed. New theoretical studies and experiments were developed, demonstrating the reliability of the procedure. Uncertainties of less than one percent were obtained when certain radioactive sources were measured. The application of the procedure to 60 Co, 22 Na, 47 Ca and 148 Pm was studied. Theoretical bases of sum peak coincidence counting were set in order to extend it as an alternative method for absolute activity determination. In this respect, theoretical studies were performed for positive and negative beta decay, and electron capture, either accompanied or unaccompanied by coincident gamma rays. They include decay schemes containing up to three daughter nuclide excited levels, for different geometrical configurations. Equations are proposed for a possible generalization of the procedure. (M.E.L.) [es

Investigation of pharmaceuticals and medical devices containing 90Y extracted from high radioactive liquid waste in spent-fuel reprocessing

International Nuclear Information System (INIS)

Hosoma, Takashi

2012-07-01

Pharmaceuticals and medical devices containing radioactive 90 Y are realized, approved and placed on the international market where three products are available in Europe and the United States, and one product in Japan. These products are used not for diagnosis but for treatment by internal irradiation. It was estimated from the deliberative report of the approval in Japan that 90 Y was extracted in Europe from high radioactive liquid waste (HALW) yielded in spent-fuel reprocessing. In this report, products placed on the market and physical properties were reviewed, reasons of the realization and conditions to realize succeeding products were estimated, extraction method was compared with other methods, technical subjects, and relevant regulations were investigated. Although a medical device containing radioactive 90 Y has been studied in Japan and one pharmaceutical product was approved, a breakthrough would be necessary to put 90 Y utilization beyond alternative treatments. The breakthrough would become be promising; for example, if conventional treatments could be supported by technical development to deliver 90 Y more sharply to the target with shorter serum half-life. Extraction of 90 Y nuclide from HALW has advantages over thermal neutron irradiation of natural nuclide, a system is envisioned where 90 Sr as a parent nuclide is separated in the reprocessing then transported to and stored in a factory of radiopharmaceuticals followed by 90 Y extraction on demand. (author)

Nuclide release calculation in the near-field of a reference HLW repository

International Nuclear Information System (INIS)

Lee, Youn Myoung; Hwang, Yong Soo; Kang, Chul Hyung

2004-01-01

The HLW-relevant R and D program for disposal of high-level radioactive waste has been carried out at Korea Atomic Energy Research Institute (KAERI) since early 1997 in order to develop a conceptual Korea Reference Repository System for direct disposal of nuclear spent fuel by the end of 2007. A preliminary reference geologic repository concept considering such established criteria and requirements as waste and generic site characteristics in Korea was roughly envisaged in 2003 focusing on the near-field components of the repository system. According to above basic repository concept, which is similar to that of Swedish KBS-3 repository, the spent fuel is first encapsulated in corrosion resistant canisters, even though the material has not yet been determined, and then emplaced into the deposition holes surrounded by high density bentonite clay in tunnels constructed at a depth of about 500 m in a stable plutonic rock body. Not only to demonstrate how much a reference repository is safe in the generic point of view with several possible scenarios and cases associated with a preliminary repository concept by conducting calculations for nuclide release and transport in the near-field components of the repository, even though enough information has not been available that much yet, but also to show a methodology by which a generic safety assessment could be performed for further development of Korea reference repository concept, nuclide release calculation study strongly seems to be necessary

EDTA fouling in dead-end ultrafiltration of low level radioactive wastewater

Energy Technology Data Exchange (ETDEWEB)

Niu, Lixia [Collaborative Innovation Center of Advanced Nuclear Energy Technology, Institute of Nuclear and New Energy Technology, Tsinghua University, Beijing 100084 (China); State Environmental Protection Key Laboratory of Microorganism Application and Risk Control (MARC), Graduate School at Shenzhen, Tsinghua University, Shenzhen, 518055 (China); Zhang, Xue [Collaborative Innovation Center of Advanced Nuclear Energy Technology, Institute of Nuclear and New Energy Technology, Tsinghua University, Beijing 100084 (China); Zhao, Xuan, E-mail: zhxinet@mail.tsinghua.edu.cn [Collaborative Innovation Center of Advanced Nuclear Energy Technology, Institute of Nuclear and New Energy Technology, Tsinghua University, Beijing 100084 (China); Hu, Hongying [Environmental Simulation and Pollution Control State Key Joint Laboratory, School of Environment, Tsinghua University, Beijing 100084 (China); State Environmental Protection Key Laboratory of Microorganism Application and Risk Control (MARC), Graduate School at Shenzhen, Tsinghua University, Shenzhen, 518055 (China)

2015-12-15

Highlights: • EDTA in LLRW caused unrecoverable UF membrane fouling. • The rejection of nuclides by UF was significantly enhanced with EDTA addition. • The nuclide (except Ag) deposition on membrane increased with EDTA addition. • Reducing EDTA in the feed water or alkaline/ultrasonic washing were suggested. - Abstract: EDTA is widely used as a detergent, and finally enters into wastewater. The influence of EDTA on ultrafiltration of low level radioactive wastewater (LLRW) was investigated under different operation conditions. As the main organic pollutant, EDTA led to unrecoverable membrane fouling and the normalized flux decreased from 100% to 85% depending on its concentration. The clogging caused by EDTA increased the surface roughness of the membrane, leading to the flux reduction. Both nuclide rejections and depositions on the membrane surfaces were enhanced with EDTA addition, due to the strong complexation of the nuclides with EDTA. However, Ag deposition on the membrane decreased slightly in the presence of EDTA, which may be caused by the stronger attraction of Ag to the unmodified membrane than that to the EDTA-modified one. Transmembrane pressure (TMP) and molecular weight cut off (MWCO) of membranes had negligible effects on membrane fouling, while the nuclide rejections by membrane and the depositions of nuclides on membrane both decreased significantly when the TMP increased to 0.2 MPa and MWCO increased from 5 kDa to 30 kDa. Based on these results, it clearly showed that EDTA even at a low concentration had strong effects on the performance of UF treating LLRW. Therefore, it is suggested for industrial application that pretreatments to reduce EDTA or alkaline/ultrasonic washing involved in UF process were necessary to reduce the nuclide depositions on the membrane surfaces and irradiation dose of membrane surface.

Calculation device for amount of heavy element nuclide in reactor fuels and calculation method therefor

International Nuclear Information System (INIS)

Naka, Takafumi; Yamamoto, Munenari.

1995-01-01

When there are two or more origins of deuterium nuclides in reactor fuels, there are disposed a memory device for an amount of deuterium nuclides for every origin in a noted fuel segment at a certain time point, a device for calculating the amount of nuclides for every origin and current neutron fluxes in the noted fuel segment, and a device for separating and then displaying the amount of deuterium nuclides for every origin. Equations for combustion are dissolved for every origin of the deuterium nuclides based on the amount of the deuterium nuclides for every origin and neutron fluxes, to calculate the current amount of deuterium nuclides for every origin. The amount of deuterium nuclides originated from uranium is calculated ignoring α-decay of curium, while the amount of deuterium nuclides originated from plutonium is calculated ignoring the generation of plutonium formed from neptunium. Deuterium nuclides can be measured and controlled accurately for every origin of the reactor fuels. Even when nuclear fuel materials have two or more nationalities, the measurement and control thereof can be conducted for every country. (N.H.)

Current status of system development to provide databases of nuclides migration

International Nuclear Information System (INIS)

Sasamoto, Hiroshi; Yoshida, Yasushi; Isogai, Takeshi; Suyama, Tadahiro; Shibata, Masahiro; Yui, Mikazu; Jintoku, Takashi

2005-01-01

JNC has developed databases of nuclides migration for safety assessment of high-level radioactive waste (HLW) repository, and they have been used in the second progress report to present the technical reliability of HLW geological disposal system in Japan. The technical level and applicability of databases have been highly evaluated even overseas. To provide the databases broadly over the world and to promote the use of the databases, we have performed the followings: 1) development of tools to convert the database format from geochemical code PHREEQE to PHREEQC, GWB and EQ3/6 and 2) set up a web site (http://migrationdb.jnc.go.jp) which enables the public to access to the databases. As a result, the number of database users has significantly increased. Additionally, a number of useful comments from the users can be applied to modification and/or update of databases. (author)

Beta-spectroscopy of long lived nuclides with a PIPS detector-setup

Directory of Open Access Journals (Sweden)

Domula Alexander R.

2017-01-01

Full Text Available Several applications in modern nuclear physics, research and engineering are limited by a lack of precise knowledge in spectral shape data for beta-decays. Specifically the interest aims to study spectral data for forbidden decays with respectively long half-lives, which is one of the central activities of our group. For the investigation of those rare beta-decays the group operates a setup of six PIPS detectors in a vacuum chamber built out of low-radioactivity materials. In the long term the setup will be used as low-background-detector for the investigation of rare beta-decays. In order to reduce the measuring-background a muon veto was installed. The characterization of the setup in the energy-range from 20..1000 keV using conversion-electrons is described. A set of useful calibration-nuclides was established to determine energy calibration and efficiencies.

Transient compartment model for the transfer of radioactivity from sub-seabed repositories

International Nuclear Information System (INIS)

Karpf, A.D.

1993-01-01

Pollution in the deep ocean can originate not only from the disposal of radioactive or chemotoxic waste but also by sea transport accidents or by deep ocean mining processes. The numerical compartment model IMPONADOR albeit developed for the assessment of a subseabed repository of radioactive vitrified waste can be applied to all these cases because of its modular character. The condition for excellent repository properties is the burial of the waste deep into the abyssal sediment. In the case of vitrified radioactive waste this had been ensured by dropping torpedo-like penetrators from the ocean surface which reached sediment depths of up to 35 m at a final speed of some 200 km/h. After intrusion the plasticity of the sediment closes the canal again tightly. The corrosion of the containers is slow at 4 C and the migration of nuclides is even slower since it can take place only by diffusion owing to the absence of any pressure heads and hence currents in the groundwater of this depth. The sediment therefore constitutes the best barrier, enhanced still by sorption. Mixing in the oceans is a complicated process but proceeds within about 500 a, the dilution of the nuclides being the actual 'barrier'. However, before reaching the marine biospere and human beings via seafood the nuclides are scavenged very effectively by sinking particles, remainders of tiny animals, and buried forever on the ocean floor. The code IMPONADOR does not only describe the time dependent equivalent doses but also displays the partition of the whole inventory into the various compartments at different times. This represents a very helpful and intuitive mean for studying the sensitivity of the individual barriers on the total results. IMPONADOR uses BASIC and runs on a PC while being able to implicate complicated informations about sediment properties and ocean currents. (orig.) [de

Separation of mobile long-lived nuclides in a simplified reprocessing

International Nuclear Information System (INIS)

Fujine, Sachio; Uchiyama, Gunzo; Kihara, Takehiro; Asakura, Toshihide; Sakurai, Tsutomu

1997-01-01

Enhancing confinement efficiency of long-lived nuclides in a simplified Purex process is the primary subject of our PARC (Partitioning Conundrum Key) R and D project. Nuclides focused here are all susceptible to diffuse into the environment and highly concerned as potential hazard among the long-lived nuclides in spent fuels. New functions in PARC concept are designed to mitigate the environmental impacts of reprocessing wastes and also to improve the economy of reprocessing in the future. Experimental work has been conducted to demonstrate the feasibility of the concept. (author)

Treatment method for stabilization of radioactive exchange resin

International Nuclear Information System (INIS)

Hideo, Oni; Takashi, Miyake; Hitoshi, Miyamoto; Toshio, Funakoshi; Yuzo, Inagaki.

1988-01-01

This is a method for eluting radioactive nuclides from a radioactive ion exchange resin in which it has been absorbed. First, the Cs in this resin is extracted using a neutral salt solution which contains Na + . The Cs that has been transferred to the neutral salt solution is absorbed and expelled by inorganic ion exchangers. Then the Co, Fe, Mn and Sr in said resin are eluted using an acidic solution; the Co, Fe, Mn and Sr that have been transferred to the acidic solution are separated from that solution by means of a diffusion dialysis vat. This process is a unique characteristic of this ion exchange resin treatment method. 1 fig

Radioactive equilibrium of uranium-bearing ores in some problems of applied geology

International Nuclear Information System (INIS)

Coulomb, R.; Girard, Ph.; Goldsztein, M.

1964-01-01

The state of equilibrium between several nuclides in radioactive relationship is determined with accuracy by the fundamental equations of radioactivity. It can be measured physically and expressed in suitable and internationally adopted units; Equilibrium - disequilibrium of uranium-bearing ores is a fairly complex phenomenon but the problem can be much simplified by well-chosen approximations in various practical field cases. The results of radiometric and radiochemical measurements lead to the interpretation of geochemical anomalies and may be used in the qualitative and quantitative estimation of uranium bearing deposits. (authors) [fr

A Study on the Nuclide Migration and Retardation Using Natural Barrier

International Nuclear Information System (INIS)

Baik, Min Hoon; Park, Chung Kyun; Kim, Seung Soo

2010-02-01

In this study, we investigated the properties of geochemical reactions and sorption of high-level radionuclides (U, Th, Am, and Np), constructed databases for the geochemical reactions and sorption of the high-level radionuclides, and developed application methodologies of the databases. For the investigation on the nuclide migration and retardation through fractured rocks in KURT, in-situ solute migration system and on-line monitoring system were installed. The migration and retardation behaviors of nuclides were investigated annually for non-sorbing, simply sorbing and multi-valent sorbing nuclides, respectively, and interactions with fracture-filling materials were also analyzed. Besides, researches difficult to perform in KURT were carried out in foreign underground research facilities as joint studies for nuclide and colloid migration. The results from domestic and foreign underground facilities were compared each other and the reliability of the domestic results were assured from this. Diffusion depths of high-level radionuclides into rock matrix were measured in KURT conditions and their diffusion properties were analyzed and evaluated. In addition, the effects of bio-mineralization and redox reactions of a nuclide and microbe on nuclide behaviors were carried out to study the effects of combined interactions between minerals and microbes on the radionuclide migration and retardation

DRENA: A model for the transport of nuclides in drainage slopes

International Nuclear Information System (INIS)

Garcia-Olivares, A.; Aguero, A.; Pinedo, P.

1994-01-01

This report presents documentation and a user's manual for program DRENA, a mathematical model of nuclides transfer in simple slopes and sections of a drainage catchment. Mathematical equations and physical principles utilized to develop the code are presented in section 2. The flowchart and some mathematic and numerical details are presented in Section 3. Section 4 presents an overview of how problems should be set up to properly use the code as well as the detailed input instructions and output results formats. One example problem, including sample input data sets and output data, are presented in Section 5. The complete program listings including comments are presented in the Appendices. Nuclides are assumed to enter the catchment via atmospheric deposition and then carried by the water runoff and the dragged sediments. The desorption/adsorption dynamics between water and sediments are considered to be in the equilibrium given by a Kd parameter, a distribution coefficient. Codell's and Einstein expressions for the caudal and concentration of dragged sediments are utilized. (Author)

DRENA: A model for the transport of nuclides in drainage slopes

International Nuclear Information System (INIS)

Garcia-Olivares, A.; Aguero, A.; Pinedo, P.

1994-01-01

This report presents documentation and a user's manual for program DRENA, a mathematical model of nuclides transfer in simple slopes and sections of a drainage catchment. Mathematical equations and physical principles utilized to develop the code are presented in section 2. The flowchart and some mathematic and numerical details are presented in Section 3. Section 4 presents an overview of how problems should be set up to properly use the code as well as the detailed input instructions and output results formats. One example problem, including sample input data sets and output data, are presented in Section 5. The complete program listings including comments are presented in the Appendices. Nuclides are assumed to enter the catchment via atmospheric deposition and then carried by the water runoff and the dragged sediments. The desorption/adsorption dynamics between water and sediments are considered to be in the equilibrium given by a Kd parameter, a distribution coefficient. Codell's and Einstein expressions for the caudal and concentration of dragged sediments are utilized. (Author) 36 refs

DRENA: A model for the transport of nuclides in drainage slopes

Energy Technology Data Exchange (ETDEWEB)

Garcia-Olivares, A.; Aguero, A.; Pinedo, P.

1994-07-01

This report presents documentation and a user's manual for program DRENA, a mathematical model of nuclides transfer in simple slopes and sections of a drainage catchment. Mathematical equations and physical principles utilized to develop the code are presented in section 2. The flowchart and some mathematic and numerical details are presented in Section 3. Section 4 presents an overview of how problems should be set up to properly use the code as well as the detailed input instructions and output results formats. One example problem, including sample input data sets and output data, are presented in Section 5. The complete program listings including comments are presented in the Appendices. Nuclides are assumed to enter the catchment via atmospheric deposition and then carried by the water runoff and the dragged sediments. The desorption/adsorption dynamics between water and sediments are considered to be in the equilibrium given by a Kd parameter, a distribution coefficient. Codell's and Einstein expressions for the caudal and concentration of dragged sediments are utilized. (Author) 36 refs.

DRENA: A model for the transport of nuclides in drainage slopes

Energy Technology Data Exchange (ETDEWEB)

Garcia-Olivares, A; Aguero, A; Pinedo, P

1994-07-01

This report presents documentation and a user's manual for program DRENA, a mathematical model of nuclides transfer in simple slopes and sections of a drainage catchment. Mathematical equations and physical principles utilized to develop the code are presented in section 2. The flowchart and some mathematic and numerical details are presented in Section 3. Section 4 presents an overview of how problems should be set up to properly use the code as well as the detailed input instructions and output results formats. One example problem, including sample input data sets and output data, are presented in Section 5. The complete program listings including comments are presented in the Appendices. Nuclides are assumed to enter the catchment via atmospheric deposition and then carried by the water runoff and the dragged sediments. The desorption/adsorption dynamics between water and sediments are considered to be in the equilibrium given by a Kd parameter, a distribution coefficient. Codell's and Einstein expressions for the caudal and concentration of dragged sediments are utilized. (Author) 36 refs.

The determination of critical nuclides in PWR waste streams

International Nuclear Information System (INIS)

Centner, B.

1993-01-01

A current method for the determination of critical nuclides in the waste streams produced by a nuclear power reactor consists in applying correlation factors or scaling factors between those critical nuclides and so called key radionuclides, which can be easily measured and are representatives for the occurrence of activation products (Co-60) and fission products (Cs-137) in the waste streams. BELGATOM (BA) has developed a code (low level waste Activity Assessment-LLWAA code). The use of the code can clarify the analytical technique lower detection level that has to be achieved for each critical nuclide, in order to accurately measure it's activity in the different types of waste. (1 tab., 1 fig.)

Nuclide migration from a bedrock repository for spent fuel

International Nuclear Information System (INIS)

Grundfelt, B.

1978-08-01

A study of the migration of radionuclides from a repository for spent, unprocessed fuel is presented. The study makes use of a unidimensional dispersion model developed at BNWL. The results show that a number of nuclides decay significantly during the migration. The doses to future man was calculated in a separate study performed at Studsvik. The dose calculations are based on the activity in-flows, presented in this report, and show that the predominant dose contribution comes from the nuclide radium-226. This nuclide is formed mainly by the decay of uranium-238 which means that the main part of the dose would arise even from a repository for non-irradiated fuel

Prospects for studies of ground-state proton decays with the Holifield Radioactive Ion Beam Facility

International Nuclear Information System (INIS)

Toth, K.S.

1994-01-01

By using radioactive ions from the Holifield Radioactive Ion Beam Facility at Oak Ridge National Laboratory it should be possible to identify many new ground-state proton emitters in the mass region from Sn to Pb. During this production and search process the limits of stability on the proton-rich side of the nuclidic chart will be delineated for a significant fraction of medium-weight elements and our understanding of the proton-emission process will be expanded and improved

A new approach to estimate nuclide ratios from measurements with activities close to background

International Nuclear Information System (INIS)

Kirchner, G.; Steiner, M.; Zaehringer, M.

2009-01-01

Measurements of low-level radioactivity often give results of the order of the detection limit. For many applications, interest is not only in estimating activity concentrations of a single radioactive isotope, but focuses on multi-isotope analyses, which often enable inference on the source of the activity detected (e.g. from activity ratios). Obviously, such conclusions become questionable if the measurement merely gives a detection limit for a specific isotope. This is particularly relevant if the presence of an isotope, which shows a low signal only (e.g. due to a short half-life or a small transition probability), is crucial for gaining the information of interest. This paper discusses a new approach which has the potential to solve these problems. Using Bayesian statistics, a method is presented which allows statistical inference on nuclide ratios taking into account both prior knowledge and all information collected from the measurements. It is shown that our method allows quantitative conclusion to be drawn if counts of single isotopes are low or become even negative after background subtraction. Differences to the traditional statistical approach of specifying decision thresholds or detection limits are highlighted. Application of this new approach is illustrated by a number of examples of environmental low-level radioactivity measurements. The capabilities of our approach for spectrum interpretation and source identification are demonstrated with real spectra from air filters, sewage sludge and soil samples.

Investigation of Nuclide Importance to Functional Requirements Related to Transport and Long-Term Storage of LWR Spent Fuel

Energy Technology Data Exchange (ETDEWEB)

Broadhead, B.L.

1995-01-01

The radionuclide characteristics of light-water-reactor (LWR) spent fuel play key roles in the design and licensing activities for radioactive waste transportation systems, interim storage facilities, and the final repository site. Several areas of analysis require detailed information concerning the time-dependent behavior of radioactive nuclides including (1) neutron/gamma-ray sources for shielding studies, (2) fissile/absorber concentrations for criticality safety determinations, (3) residual decay heat predictions for thermal considerations, and (4) curie and/or radiological toxicity levels for materials assumed to be released into the ground/environment after long periods of time. The crucial nature of the radionuclide predictions over both short and long periods of time has resulted in an increased emphasis on thorough validation for radionuclide generation/depletion codes. Current radionuclide generation/depletion codes have the capability to follow the evolution of some 1600 isotopes during both irradiation and decay time periods. Of these, typically only 10 to 20 nuclides dominate contributions to each analysis area. Thus a quantitative ranking of nuclides over various time periods is desired for each of the analysis areas of shielding, criticality, heat transfer, and environmental dose (radiological toxicity). These rankings should allow for validation and data improvement efforts to be focused only on the most important nuclides. This study investigates the relative importances of the various actinide, fission-product, and light-element isotopes associated with LWR spent fuel with respect to five analysis areas: criticality safety (absorption fractions), shielding (dose rate fractions), curies (fractional curies levels), decay heat (fraction of total watts), and radiological toxicity (fraction of potential committed effective dose equivalent). These rankings are presented for up to six different burnup/enrichment scenarios and at decay times from 2 to

Estimation of radioactive effluents concentrations in the vicinity of nuclear power plant

International Nuclear Information System (INIS)

Arsov, Lj.

1977-01-01

This paper deals with the problem of mathematical prediction of radioactive effluent concentrations around nuclear power plants. This mathematical model which describes the behaviour of the effluent in the atmosphere here in after is expanded and adapted for radioactive effluent treatment. In this way the mathematical model includes the description of the following effects: the rise of plume caused by its vertical momentum and its heat content, wind velocity profile and vertical growth of the coefficient of diffusion, fallout under gravity, ground deposition, precipitation scavenging, and radioactive decay. The advanced computer program DIFFUS has been applied to evaluate the ground concentration of the nuclides of I, which constitute the greatest risk for population.(author)

Evaluation of induced radioactivity in 10 MeV-electron irradiated spices, (1); [gamma]-ray measurement

Energy Technology Data Exchange (ETDEWEB)

Furuta, Masakazu; Katayama, Tadashi; Ito, Norio; Mizohata, Akira; Matsunami, Tadao; Shibata, Setsuko; Toratani, Hirokazu (Osaka Prefectural Univ., Sakai (Japan). Research Inst. for Advanced Science and Technology); Takeda, Atsuhiko

1994-02-01

Black pepper, white pepper, red pepper, ginger and turmeric were irradiated with 10 MeV electrons from a linear accelerator to a dose of 100 kGy and radioactivity was measured in order to estimate induced radioactivity in the irradiated foods. Induced radioactivity could not be detected significantly by [gamma]-ray spectrometry in the irradiated samples except for spiked samples which contain some photonuclear target nuclides in the list of photonuclear reactions which could produce radioactivity below 10 MeV. From the amount of observed radioactivities of short-lived photonuclear products in the spiked samples and calculation of H[sub 50] according to ICRP Publication 30, it was concluded that the induced radioactivity and its biological effects in the 10 MeV electron-irradiated natural samples were negligible in comparison with natural radioactivity from [sup 40]K contained in the samples. (author).

Radioactivity Measurements on Glazed Ceramic Surfaces.

Science.gov (United States)

Hobbs, T G

2000-01-01

A variety of commonly available household and industrial ceramic items and some specialty glass materials were assayed by alpha pulse counting and ion chamber voltage measurements for radioactivity concentrations. Identification of radionuclides in some of the items was performed by gamma spectroscopy. The samples included tableware, construction tiles and decorative tiles, figurines, and other products with a clay based composition. The concentrations of radioactivity ranged from near background to about four orders of magnitude higher. Almost every nuclide identification test demonstrated some radioactivity content from one or more of the naturally occurring radionuclide series of thorium or uranium. The glazes seemed to contribute most of the activity, although a sample of unglazed pottery greenware showed some activity. Samples of glazing paints and samples of deliberately doped glass from the World War II era were included in the test, as was a section of foam filled poster board. A glass disc with known (232)Th radioactivity concentration was cast for use as a calibration source. The results from the two assay methods are compared, and a projection of sensitivity from larger electret ion chamber devices is presented.

A survey of radioactive levels of agricultural products in Saitama prefecture

Energy Technology Data Exchange (ETDEWEB)

Motegi, Misako; Miyake, Sadaaki; Oosawa, Takashi; Nakazawa, Kiyoaki [Saitama Inst. of Public health, Saitama (Japan)

1997-09-01

Past atmospheric nuclear testing which have been conducted frequently, have caused environmental pollution due to the diffusion of radioactive substances into the atmosphere and from the radioactive fallout. The environmental pollution from nuclear testing into the atmosphere has resulted in the radioactive contamination in agricultural products and has continued for a long time. The radioactive contamination of agricultural products occurs through air, water and soil which were contaminated by radioactive fallout. In this paper, for the purpose of analyzing the extent of the radioactive contamination levels in the agricultural products of Saitama Prefecture, spinach, green soybeans, dried shiitake and welsh onion, were selected among products, as the amount of the harvest is abundant in all of Japan. Radioactivity concentration was investigated by gamma-ray spectrometry and radiochemical analysis. The radioactivity concentrations of artificial radioactive nuclides, cesium-137 ({sup 137}Cs) and strontium-90 ({sup 90}Sr), were detected in the range which is considered to be the result of radioactive fallout. Moreover, in order to examine the effect on radioactivity concentrations in agricultural products by culinary processing, the raw agricultural products were boiled, and their radioactivity concentrations were compared with the raw produce. The radioactivity concentrations in the boiled were lower than those in the raw produce. (author)

A survey of radioactive levels of agricultural products in Saitama prefecture

International Nuclear Information System (INIS)

Motegi, Misako; Miyake, Sadaaki; Oosawa, Takashi; Nakazawa, Kiyoaki

1997-01-01

Past atmospheric nuclear testing which have been conducted frequently, have caused environmental pollution due to the diffusion of radioactive substances into the atmosphere and from the radioactive fallout. The environmental pollution from nuclear testing into the atmosphere has resulted in the radioactive contamination in agricultural products and has continued for a long time. The radioactive contamination of agricultural products occurs through air, water and soil which were contaminated by radioactive fallout. In this paper, for the purpose of analyzing the extent of the radioactive contamination levels in the agricultural products of Saitama Prefecture, spinach, green soybeans, dried shiitake and welsh onion, were selected among products, as the amount of the harvest is abundant in all of Japan. Radioactivity concentration was investigated by gamma-ray spectrometry and radiochemical analysis. The radioactivity concentrations of artificial radioactive nuclides, cesium-137 ( 137 Cs) and strontium-90 ( 90 Sr), were detected in the range which is considered to be the result of radioactive fallout. Moreover, in order to examine the effect on radioactivity concentrations in agricultural products by culinary processing, the raw agricultural products were boiled, and their radioactivity concentrations were compared with the raw produce. The radioactivity concentrations in the boiled were lower than those in the raw produce. (author)

R and D projects for disposal concepts for special radioactive wastes

International Nuclear Information System (INIS)

1983-01-01

Updated requirements for the elaboration of reference methods or back-up methods for the conditioning and ultimate storage of special radioactive wastes are worked out. Subsequently, the present state-of-art and ongoing studies are analyzed. Special radioactive wastes collected in collecting points, or produced in medicine and industry are included in the paper. With special unclear wastes, the emphasis is on wastes from LWR-type reactors and those from the unclear fuel cycle. The PTB data base is to by complemented by the characterization of waste compounds with volatile nuclides. 16 specialist contributions have been included in the data base. (HP) [de

An analysis of the correlation between dust storms in Korea and 137Cs nuclide concentration

International Nuclear Information System (INIS)

Choi, Soo-won; Kim, Jeong-hun; Shin, Sang-hwa; Hwang, Joo-ho

2008-01-01

Dust storms occur in Korea during spring time when fine dust is blown in from the far western regions of western China and Mongolia. A fine powdery dust is blown up into the sky and enters the upper reaches of the atmosphere where it is carried easterly across China then slowly falls to the ground on the Korean peninsula and Japan. The dust originates mostly in the Gobi dessert of China, as well as the yellow earth regions in the middle and upper streams of the Yellow river in China. Previous studies on dust storms have been limited to following or estimating their courses, distribution and frequency, or distribution of the heavy metals they transmit. However, since radionuclides exist in the dust, they must also exist in the dust storms. In this study, we analyzed the correlation of :1 37 Cs nuclide concentration based on a count of annual dust storm occurrence in the city of Suwon, South Korea and assessed seasonal differences of 137 Cs nuclide concentration

Terms and definitions in the field of radiological technique

International Nuclear Information System (INIS)

1978-04-01

Nuclides and their symbols: Nuclide, symbol for nuclides; Nuclear processes: Nuclear transformation, isomeric transition; Radioactive substances; Radiation of radioactive substances: Alpha radiation, beta radiation, k radiation, gamma radiation, conversion electrons, annihilation radiation, neutron radiation; Activity, specific activity, and activity concentration; Characteristic constants of radio nuclides: Decay constant, lifetime, half-life, specific gamma-ray constant, conversion coefficient; Decay series: Radioactive decay series, radioactive equilibrium; Nuclides with special names and symbols: Hydrogen isotopes, nuclides of the natural decay series. (orig.) [de

Yearly plan of safety research on environmental radioactivity for 1996 - 2000

International Nuclear Information System (INIS)

1996-01-01

'Yearly Plan of Safety Research on Environmental Radioactivity' proposed from the special meeting for safety research of environmental radioactivity on December 14, 1995 was investigated by Nuclear Safety Commission. And the safety research of environmental radioactivity in Japan was decided to be pursued according to the plan. The contents of this plan consisted of the purpose and the contents of research as well as the research period and the facilities to be done for each theme. The following themes were included; 1) study on environment·radiation dose and study on radiation exposure reduction. 2) study on biological effects of radiation. 3) study on internal exposure by specified nuclides. 4) study on medical measures for acute radiation exposure. 5) study on assessment of nuclear safety. 6) investigation on radioactivities released from various nuclear facilities in Japan to demonstrate their safety. (M.N.)

Behaviour of transuranic nuclides in coastal environment

International Nuclear Information System (INIS)

Pillai, K.C.; Mathew, E.; Matkar, V.M.; Dey, N.N.; Abani, M.C.; Chhapgar, B.F.; Mullay, C.D.

1982-01-01

In view of the nuclear technological developments, the potential for contamination of marine environment with transuranic nuclides has increased. In this context it is necessary to know not only the current levels of these artificial nuclides but there is also a need to understand the physico-chemical, biological and geochemical behaviour of transuranics to evaluate their significance in the marine environment. Studies on these aspects have been carried out in the coastal environment of the west coast of India, near Bombay. The results obtained and conclusions drawn from the various investigations carried out are given in this document

Stable isotope analysis of the human body. What isotopes in our tissue can reveal and what not; Stabilisotopenanalysen am Menschen. Was die Isotopie unseres Koerpergewebes ueber uns verraet- und was nicht

Energy Technology Data Exchange (ETDEWEB)

Goerger, Marlene [Technische Univ. Darmstadt (Germany)

2016-07-01

Most isotopes in the natural environment are stable but there are radioactive isotopes. Premordial radionuclides are nuclides that exist since the development of the earth crust. Cosmogenic radionuclides are generated due to cosmic radiation (protons, electrons, ionized atoms) - for instance C-14. Radiogenic nuclides are daughter products of radioactive nuclei. Anthropogenic radionuclides are generated due to human activities. Deviations from a ''normal'' isotope distribution are used for environmental impact analysis and forensic purposes. The human provenance project was stopped.

Radioactivity of neutron-irradiated cat's-eye chrysoberyls

Energy Technology Data Exchange (ETDEWEB)

Tang, S.M. E-mail: phytsm@leonis.nus.edu.sg; Tay, T.S

1999-04-02

The recent report of marketing of radioactive chrysoberyl cat's-eyes in South-East Asian markets has led us to use an indirect method to estimate the threat to health these color-enhanced gemstones may pose if worn close to skin. We determined the impurity content of several cat's-eye chrysoberyls from Indian States of Orissa and Kerala using PIXE, and calculated the radioactivity that would be generated from these impurities and the constitutional elements if a chrysoberyl was irradiated by neutrons in a nuclear reactor for color enhancement. Of all the radioactive nuclides that could be created by neutron irradiation, only four ({sup 46}Sc, {sup 51}Cr, {sup 54}Mn and {sup 59}Fe) would not have cooled down within a month after irradiation to the internationally accepted level of specific residual radioactivity of 2 nCi/g. The radioactivity of {sup 46}Sc, {sup 51}Cr and {sup 59}Fe would only fall to this safe limit after 15 months and that of {sup 54}Mn could remain above this limit for several years.

Radioactivity, radiation protection and monitoring during dismantling of light-water reactors

International Nuclear Information System (INIS)

Hummel, L.; Zech, J.B.

2005-01-01

Based on the radioactivity inventory in the systems and components of light-water reactors observed during operation, the impact of actions during plant emptying after the conclusion of power operation and possible subsequent long-term safe enclosure concerning the composition of the nuclide inventory of the plant to be dismantled will be described. Derived from this will be the effects on radioactivity monitoring in the plant, physical radiation protection monitoring, and the measured characterization of the residual materials resulting from the dismantling. The impact of long-term interim storage will also be addressed in the discussion. The talk should provide an overview of the interrelationships between source terms, decay times and the radioactivity monitoring requirements of the various dismantling concepts for commercial light-water reactors. (orig.)

Environmental radioactivity at the National Nuclear Research Centre, Pelindaba

International Nuclear Information System (INIS)

Brits, R.J.N.; Van der Westhuizen, G.S.H.; Annandale, J.

1983-06-01

The revised environmental survey program, introduced during 1970 with the emphasis on monitoring of the critical paths of exposure of the general public, was continued in 1982. Results of determinations of both gross radioactivity and individual nuclides in samples of fish and water (which are critical materials for liquid-effluent releases) from the Hartebeespoort Dam and from the Crocodile River, are given and discussed. Results of 131 I, 90 Sr and gamma-spectrometric analyses of milk, the critical material for releases to the atmosphere, are presented. Results are given of regular investigations of the composition of airborne releases to the atmosphere and liquid-effluent releases to the Crocodile River, performed in order to detect other possible critical nuclides. Levels of deposited and airborne activity from nuclear-bomb tests are reported. Due to absence of fresh fallout material the levels for most fission products have fallen below the limit of detection. No environmental radioactivity due to releases from the Pelindaba site could be detected above the natural background or accumulated fallout levels. Unplanned releases of UF 6 occur sometimes. Accordingly, some of the environmental samples were also analysed for uranium. The results obtained so far do not indicate an increase in uranium levels in the environment

Map of calculated radioactivity of fission product, (4)

International Nuclear Information System (INIS)

Takeda, Tsuneo

1978-07-01

The overall radioactivities of fission products depending on irradiation time and cooling time were calculated for 18 different neutron fluxes, which are presented in contour maps and tables. Irradiation condition etc. are the followings: neutron flux (n sub(th)) 1 x 10 12 - 6.8 x 10 14 n/cm 2 /sec, uranium quantity 1 mole (6 x 10 23 atoms, ca. 271 g UO 2 ), U-235 enrichment 2.7%, irradiation time 60. - 6 x 10 7 sec (1 min - 1.9 y), cooling time 0. and 60. - 6 x 10 7 sec (1 min - 1.9 y). The enrichment value represents those for LWRs. To calculate the overall radioactivities, 595 fission product nuclides were introduced. Overall radioactivities calculations were made for 68,000 combinations of irradiation time, cooling time and neutron flux. The many complex decay chains of fission products were treated with CODAC-No.6 computer code. (author)

Retardation of escaping nuclides from a final depository

International Nuclear Information System (INIS)

Neretnieks, I.

1977-09-01

study has been made on retardation of radionuclides in various materials, which could be suited for use in the final repository. A literature survey has shown that except for Cs and Sr very little is known on ion exchange equilibria in ground water surroundings. Measurements were made to determine equilibrium data for Cs, Sr, Eu and U in five natural zeolites, which could be used as filling material. Diffusivities in zeolite particles and bbeds as well as clay beds were also determined. With the aid of these data the function of the ion exchange barrier was investigated. The barrier is so short that the nuclide transport is by diffusion. An 0.2 m barrier of a zeolite will delay Cs and Sr so long that they will decay totally. Am 241 will also be considerably delayed. An 0.2 m clay-quartz barrier will have very little effect on these nuclides. A 1 m clay-quartz barrier will have about the same effect as an 0.2 m zeolite barrier. Most other nuclides have so long lives that they will only be delayed, but not sufficiently long to decay. He rock itself interacts with many of the radionuclides. A simple model has been made to describe the nuclide retardation and dispersion in fissured rock. With the aid of this, tracer experiments in actual underground rock have been analysed

A nuclear data library for activity determinations of selected nuclides

International Nuclear Information System (INIS)

Baard, J.H.

1991-11-01

This report describes the GAMLIB 1-5 library, which is used in the calculation of the activity of radionuclides present in the gamma-ray spectra of irradiated neutron fluence detectors. The library contains all constants needed to calculate the activity for reactions normally applied in neutron fluence determinations, performed in irradiation experiments in the HFR. It also contains the nuclide constants for the activity calculation of gamma-ray measurements of U and Pu samples. The library consists of two kinds of tables, the first containing gamma-ray energies and gamma-ray emission probabilities with their uncertainties and the nuclide code, the other the nuclide code, decay constant, gamma -ray energies and gamma-ray emission probabilities. No cross-section data are stored in this library. All the relevant dat of the Nuclear Data Guide (Dordrecht, Kluwer 1989) have been used as base for this library. Other data have been obtained from recent literature. This library comprises 155 nuclides and 1115 gamma-ray energies. (author). 9 refs

Assessment of radioactive residues arising from radiolabel instability in a multiple dose tissue distribution study in rats

International Nuclear Information System (INIS)

Slatter, J.G.; Sams, J.P.; Easter, J.A.

2003-01-01

Our study objectives were to quantitatively determine the effect of radiolabel instability on terminal phase radioactive tissue residues in a multiple dose tissue distribution study, to quantitatively compare tissue residue artifacts (non drug-related radioactivity) from two chemically-distinct radiolabel locations, and to conduct a definitive multiple dose tissue distribution study using the better of the two radiolabeled compounds. We compared the excretion and tissue distribution in rats of [ 14 C]linezolid, radiolabeled in two different locations, after 7 consecutive once daily [ 14 C] oral doses. The radiolabels were in the acetamide (two carbon) and oxazolidinone (isolated carbon) functional groups. Terminal phase tissue residue and excretion data were compared to data from rats dosed orally with [ 14 C]sodium acetate. Drug-related radioactivity was excreted rapidly over 24 h. After a single dose, the acetamide and oxazolidinone radiolabel sites both gave 3% of dose as exhaled 14 CO 2 . After 7 daily [ 14 C] oral doses, terminal phase radioactive tissue residues were higher from the acetamide radiolabel, relative to the oxazolidinone radiolabel, and were primarily not drug-related. In the definitive tissue distribution study, low concentrations of drug-related radioactivity in skin and thyroid were observed. We conclude that although small amounts of radiolabel instability do not significantly affect single dose tissue radioactivity C max and area under the curve (AUC), artifacts arising from radiolabel instability can prolong the apparent terminal phase half life and complicate study data interpretation. When possible, it is always preferable to use a completely stable radiolabel site. (author)

Assessment of radioactive residues arising from radiolabel instability in a multiple dose tissue distribution study in rats

Energy Technology Data Exchange (ETDEWEB)

Slatter, J.G. [Pharmacia Corp., Peapack, NJ (United States); Sams, J.P.; Easter, J.A. [Pharmacia Corp., Kalamazoo, MI (United States)] [and others

2003-05-01

Our study objectives were to quantitatively determine the effect of radiolabel instability on terminal phase radioactive tissue residues in a multiple dose tissue distribution study, to quantitatively compare tissue residue artifacts (non drug-related radioactivity) from two chemically-distinct radiolabel locations, and to conduct a definitive multiple dose tissue distribution study using the better of the two radiolabeled compounds. We compared the excretion and tissue distribution in rats of [{sup 14}C]linezolid, radiolabeled in two different locations, after 7 consecutive once daily [{sup 14}C] oral doses. The radiolabels were in the acetamide (two carbon) and oxazolidinone (isolated carbon) functional groups. Terminal phase tissue residue and excretion data were compared to data from rats dosed orally with [{sup 14}C]sodium acetate. Drug-related radioactivity was excreted rapidly over 24 h. After a single dose, the acetamide and oxazolidinone radiolabel sites both gave 3% of dose as exhaled {sup 14}CO{sub 2}. After 7 daily [{sup 14}C] oral doses, terminal phase radioactive tissue residues were higher from the acetamide radiolabel, relative to the oxazolidinone radiolabel, and were primarily not drug-related. In the definitive tissue distribution study, low concentrations of drug-related radioactivity in skin and thyroid were observed. We conclude that although small amounts of radiolabel instability do not significantly affect single dose tissue radioactivity C{sub max} and area under the curve (AUC), artifacts arising from radiolabel instability can prolong the apparent terminal phase half life and complicate study data interpretation. When possible, it is always preferable to use a completely stable radiolabel site. (author)

Research on rejection performance of reverse osmosis to nickel in simulated radioactive wastewater

International Nuclear Information System (INIS)

Kong Jinsong; Wang Xiaowei

2013-01-01

In order to reveal the rejection performance of the reverse osmosis applied in the radioactive wastewater treatment, treatment experiments were carried out on a pilot reverse osmosis equipment using wastewater containing nickel nuclide. Results showed that the rejection ratio of reverse osmosis to nickel was almost not affected by the operation pressure and the ratio of reclaiming, and had no direct relation with the salt rejection ratio. The ratio of nickel rejection reached 95% in the experiment condition and could meet the requirement on the disposal of radioactive wastewater produced by nuclear powered installations. (authors)

Research on rejection performance of reverse osmosis to cobalt in simulated radioactive wastewater

International Nuclear Information System (INIS)

Kong Jinsong; Tian Yanjie

2012-01-01

In order to reveal the rejection performance of the reverse osmosis applied in the radioactive wastewater treatment, treatment experiments were carried out on a pilot reverse osmosis equipment using wastewater containing cobalt nuclide. Results showed that the rejection ratio of reverse osmosis to cobalt was almost not affected by the operation pressure and the ratio of reclaiming, and had no direct relation with the salt rejection ratio. The ratio of cobalt rejection reached 90% in the experiment condition and could meet the requirement on the disposal of radioactive wastewater produced by nuclear powered installations. (authors)

Research on rejection performance of reverse osmosis to manganese in simulated radioactive wastewater

International Nuclear Information System (INIS)

Kong Jinsong; Wang Xiaowei

2012-01-01

In order to reveal the performance of reverse osmosis applied in the radioactive wastewater treatment, treatment experiments are carried out on a pilot RO equipment using wastewater containing manganese nuclide. Results show that the rejection ratio of RO to manganese is almost not influenced by the operation pressure and the ration of reclaiming, and has no direct relation with the salt rejection ratio. The ratio of manganese rejection is more than 95% and can meet the requirement on the disposal of radioactive wastewater produced by pressurized water reactors. (authors)

Normal and Abnormal Scenario Modeling with GoldSim for Radioactive Waste Disposal System

International Nuclear Information System (INIS)

Lee, Youn Myoung; Jeong, Jong Tae

2010-08-01

A modeling study and development of a total system performance assessment (TSPA) template program, by which an assessment of safety and performance for the radioactive waste repository with normal and/or abnormal nuclide release cases could be assessed has been carried out by utilizing a commercial development tool program, GoldSim. Scenarios associated with the various FEPs and involved in the performance of the proposed repository in view of nuclide transport and transfer both in the geosphere and biosphere has been also carried out. Selected normal and abnormal scenarios that could alter groundwater flow scheme and then nuclide transport are modeled with the template program. To this end in-depth system models for the normal and abnormal well and earthquake scenarios that are conceptually and rather practically described and then ready for implementing into a GoldSim TSPA template program are introduced with conceptual schemes for each repository system. Illustrative evaluations with data currently available are also shown

Characterization on the Fracture system in jurassic granitic rocks: Kosung and Yusung areas

Energy Technology Data Exchange (ETDEWEB)

Kim, Kyung Su; Bae, Dae Seok; Kim, Chun Soo; Park, Byung Yoon; Koh, Yong Kweon

2001-03-01

The safety of waste disposal can be achieved by a complete isolation of radioactive wastes from biosphere or by a retardation of nuclide migration to reach an acceptable dose level. For the deep geological disposal of high-level radioactive waste, the potential pathways of nuclide primarily depend on the spatial distribution characteristics of conductive fractures in rock mass. Major key issues in the quantification of fracture system for a disposal site are involved in classification criteria, hydraulic parameters, geometry, field investigation methods etc. This research aims to characterize the spatial distribution characteristics of regional lineaments and background fractures in eastern and western-type granite rock mass.

A study on the characteristics of site-scale fracture system in granite and volcanic rock