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AbstractAbstract
[en] The 99m Tc is the more used radioisotope in nuclear medicine, used in 80% of procedures of nuclear medicine in the world. This is due to their characteristics practically ideal for the diagnostic. The 99mTc is obtained by decay of the 99Mo, which can produce it by irradiating enriched targets in 98Mo, or as fission product, irradiating uranium targets or by means of homogeneous solution reactors. The pattern of the used reactor in the neutron analysis possesses a liquid fuel composed of uranyl nitrate dissolved in water with the attach of nitric acid. This solution is contained in a cylindrical recipient of stainless steel reflected with light water. The reactor is refrigerated by means of an helicoidal heat exchanger immersed in the fuel solution. The heat of the fuel is removed by natural convection while the circulation of the water inside the exchanger is forced. The control system of the reactor consists on 6 independent cadmium bars, with followers of water. An auxiliary control system can be the level of the fuel solution inside container tank, but it was not included in the pattern in study. One studies the variations of the reactivity of the system due to different phenomena. An important factor during the normal operation of the reactor is the variation of temperature taking to a volumetric expansion of the fuel and ghastly effects in the same one. Another causing phenomenon of changes in the reactivity is the variation of the concentration of uranium in the combustible solution. An important phenomenon in this type of reactors is the hole fraction in the nucleus I liquidate due to the radiolysis and the possible boil of the water of the combustible solution. Some of the possible cases of abnormal operation were studied as the lost one of coolant in the secondary circuit of the heat exchanger, the introduction and evaporation of water in the nucleus. The reactivity variations were studied using the codes of I calculate MCNP, WIMS and TORT. All the calculations show a safe neutronic behavior of this class of reactors with big negative reactivity coefficients. The burnt of the fuel and their effects in the reactivity is small considering the good production and efficiency. (Author)
Original Title
Analisis de un reactor de solucion homogenea para produccion de 99 Mo
Primary Subject
Source
2007; 10 p; 25. SMSR Annual Meeting Co-sponsored by AMEE; Contribution of nuclear energy to the sustainable development of Latin-America; Cancun, Q.R. (Mexico); 1-5 Jul 2007; 18. Annual SNM Congress; Contribution of nuclear energy to the sustainable development of Latin-America; Cancun, Q.R. (Mexico); 1-5 Jul 2007; 2007 LAS/ANS Symposium; Contribution of nuclear energy to the sustainable development of Latin-America; Cancun, Q.R. (Mexico); 1-5 Jul 2007; ISBN 978-968-9353-00-3;
; Available from the Instituto Nacional de Investigaciones Nucleares, Centro de Informacion y Documentacion Nuclear, 52045 Ocoyoacac, Estado de Mexico (MX). e-mail: svp@nuclear.inin.mx; rbc@nuclear.inin.mx

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BARYONS, BETA DECAY RADIOISOTOPES, BETA-MINUS DECAY RADIOISOTOPES, COMPUTER CODES, CONTROL SYSTEMS, DAYS LIVING RADIOISOTOPES, ELEMENTARY PARTICLES, ELEMENTS, ENERGY SOURCES, EVEN-ODD NUCLEI, FERMIONS, FLUID FUELED REACTORS, FUELS, HADRONS, HOMOGENEOUS REACTORS, HOURS LIVING RADIOISOTOPES, INTERMEDIATE MASS NUCLEI, INTERNAL CONVERSION RADIOISOTOPES, ISOMERIC TRANSITION ISOTOPES, ISOTOPES, LIQUID HOMOGENEOUS REACTORS, MATERIALS, METALS, MOLYBDENUM ISOTOPES, NUCLEI, NUCLEONS, ODD-EVEN NUCLEI, RADIOISOTOPES, REACTOR MATERIALS, REACTORS, TECHNETIUM ISOTOPES, WATER COOLED REACTORS, WATER MODERATED REACTORS, YEARS LIVING RADIOISOTOPES
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Marinkovicj, N.
Institut za Nuklearne Nauke Boris Kidric, Belgrade (Yugoslavia)
Institut za Nuklearne Nauke Boris Kidric, Belgrade (Yugoslavia)
AbstractAbstract
[en] CRISPV (Criticality and Spectrum code) is a multigroup neutron spectrum code for homogeneous reactor cores and is actually a somewhat modified version of the original CRISP programme. It is a combination of DATAPREP-II and BIGG-II programmes. It is assumed that the reactor cell is a cylindrical fuel rod in the light or heavy water moderator. DATEPREP-II CODE forms the multigroup data for homogeneous reactor and prepares the input parameters for the BIGG-II code. It has its own nuclear data library on a separate tape in binary mode. BIGG-II code is a multigroup neutron spectrum and criticality code for a homogenized medium. It has as well its own separate data library. In the CRISPV programme the overlay structure enables automatic handling of data calculated in the DATAPREP-II programme and needed in the BIGG-II core. Both programmes are written in FORTRAN for CDC 3600. Using the programme is very efficient and simple
Original Title
Crispv - opis i uputstvo za koriscenje programa
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Source
nd; 44 p; 3 tables, 11 refs., 4 appls.
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Report
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Dedi Hermawan, E-mail: d.hermawan@bapeten.go.id
Proceedings of the nuclear safety seminar 2015: Strengthening of nuclear oversight for the welfare and independence of the nation2015
Proceedings of the nuclear safety seminar 2015: Strengthening of nuclear oversight for the welfare and independence of the nation2015
AbstractAbstract
[en] Aqueous Homogeneous Reactor is a nuclear reactor with fuel solution and homogeneously mixed with a moderator and being developed as a means to produce medical isotopes. To perform its function of producing radioisotope, AHR will require radioisotope separation facility. In general, radioisotope separation facilities connected with AHR, will consist of several parts, such as extraction section, waste and gas management section, iodine separation section, purification section, delivery section and also the connecting sections. Results of the assessment shows that several safety related things needs to be considered for the radioisotopes separation facility of AHR. Exposure to high radiation from the fuel solution that will enter radioisotopes separation facilities will need a shielded room to hold or reduce exposure to workers. The use of materials particularly on the piping must be resistant to corrosion or against radiation. The potential leak or absorption gas saturation of iodine and other fission products also needs to be considered. It should also be noted related waste generated from this facility such as fuel solution, absorption materials, fission product gases, pipes or other process materials. (author)
Original Title
Kajian keselamatan fasilitas pemisahan radioisotop yang berbasiskan Aqueous Homogeneous Reactor (AHR)
Primary Subject
Source
Budi Rohman; Liliana Yetta Pandi; Syahrir; Azhar; Ishak (BAPETEN, Jakarta (Indonesia)) (eds.); M Subekti (ed.) (BATAN, Jakarta (Indonesia)); Djarwani (ed.) (UI, Depok (Indonesia)); Zaki Suud (ed.) (ITB, Bandung (Indonesia)); Sihana (ed.) (UGM, Yogyakarta (Indonesia)); Nuclear Energy Regulatory Agency, Jakarta (Indonesia); [202 p.]; ISSN 1412-3258;
; Aug 2015; p. 63-66; Nuclear safety seminar 2015; Seminar keselamatan nuklir 2015; Jakarta (Indonesia); 13 Aug 2015; Also available from Center for Utilization of Informatics and Region Strategic Nuclear, National Nuclear Energy Agency, Puspiptek Area, Fax. 62-21-7560895, Serpong, Tangerang Selatan 15314 (ID); 8 refs.; 3 figs.

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AbstractAbstract
No abstract available
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Journal Article
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Nuclear Science and Engineering; v. 47(1); p. 132-139
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AbstractAbstract
[en] In this paper a general polynomial expression is obtained for the Bickley and Exponential integral functions (Kin and En, n 1-7), where only coefficients are different. These coefficients can be obtained, depending on the accuracy we require. One problem of a homogeneous reactor has been considered here where it is shown that a polynomial of limited accuracy also can give converged results, depending upon the problem. (author)
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AbstractAbstract
No abstract available
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16. nuclear science symposium; San Francisco, Calif; 29 Oct 1969
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Journal Article
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Progress Report
Journal
IEEE (Inst. Elec. Electron. Eng.), Trans. Nucl. Sci; v. NS-17(1); p. 549-554
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Azizul Khakim; Arif Isnaeni, E-mail: a.khakim@bapeten.g.id
Proceedings of the nuclear safety seminar 2015: Strengthening of nuclear oversight for the welfare and independence of the nation2015
Proceedings of the nuclear safety seminar 2015: Strengthening of nuclear oversight for the welfare and independence of the nation2015
AbstractAbstract
[en] One of the phenomena at Aqueous Homogeneous Reactor (AHR) of uranium solution fuel is radiolysis process that breaks the water molecules into oxygen and hydrogen gases by both neutron and gamma radiations. The reduction of water molecules in the solution causes the concentration of uranium solution increases and eventually leads to core reactivity change. As AHR is equipped with recombiner to recombine the oxygen and hydrogen gases into water, the fuel concentration will become lower. This will also induce core reactivity change. The periodic changes in reactivity due to fluctuation in uranium concentration will lead to power fluctuation. The paper aims at determining reactivity change due to the change in uranium concentration, and other reactivity change such as doppler effect. The analyses were performed using two Monte Carlo method codes, MCNP and MVP. For the reactor being analyzed, with power of 20 kW and 1 kW/l of power density, has the doppler reactivity coefficient -1,01 × 10-2 %dk/k. This system also has strong negative feedback reactivity from void generation. (author)
Original Title
Perilaku perubahan reaktivitas pada reaktor AHR
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Source
Budi Rohman; Liliana Yetta Pandi; Syahrir; Azhar; Ishak (BAPETEN, Jakarta (Indonesia)) (eds.); M Subekti (ed.) (BATAN, Jakarta (Indonesia)); Djarwani (ed.) (UI, Depok (Indonesia)); Zaki Suud (ed.) (ITB, Bandung (Indonesia)); Sihana (ed.) (UGM, Yogyakarta (Indonesia)); Nuclear Energy Regulatory Agency, Jakarta (Indonesia); [202 p.]; ISSN 1412-3258;
; Aug 2015; p. 18-23; Nuclear safety seminar 2015; Seminar keselamatan nuklir 2015; Jakarta (Indonesia); 13 Aug 2015; Also available from Center for Utilization of Informatics and Region Strategic Nuclear, National Nuclear Energy Agency, Puspiptek Area, Fax. 62-21-7560895, Serpong, Tangerang Selatan 15314 (ID); 10 refs.; 3 tabs.; 6 figs.

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ALTERNATIVE FUELS, CALCULATION METHODS, CHEMICAL RADIATION EFFECTS, CHEMICAL REACTIONS, DECOMPOSITION, DISPERSIONS, ELEMENTS, ENERGY SOURCES, FLUID FUELED REACTORS, FLUIDS, FUELS, HOMOGENEOUS MIXTURES, HOMOGENEOUS REACTORS, LIQUID FUELS, MATERIALS, MIXTURES, NONMETALS, NUCLEAR FUELS, RADIATION EFFECTS, REACTOR MATERIALS, REACTORS, SOLUTIONS, SYNTHETIC FUELS
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Dedi Hermawan; Nofrijon Sofyan, E-mail: d.hermawan@bapeten.go.id
Proceedings of the nuclear safety seminar 2015: Strengthening of nuclear oversight for the welfare and independence of the nation2015
Proceedings of the nuclear safety seminar 2015: Strengthening of nuclear oversight for the welfare and independence of the nation2015
AbstractAbstract
[en] Technetium-99m, which is generated from the decay of molybdenum-99, is the most commonly used medical radioisotope in the world. To produce molybdenum-99, nuclear reactor types namely aqueous homogeneous reactor (AHR) are being developed by many researcher. Although many AHRs-related research have been done, references that discuss the aspects of the material are rarely available. At the same time, material is one of important aspects to consider in designing AHR. In this case, one thing that needs to be investigated in relation to the structural integrity of AHR vessels is the stress caused by the pressure and temperature of the reactor operation. The design of vessels needs to consider many aspects such as normal operating conditions and also a possibility of accident or abnormal conditions. This research was performed through a computer simulation by using finite element method (FEM) available in ANSYS. The simulation results shows that pressure and temperature in the vessel affect the stress of the vessel material. Higher pressure and temperature in the vessel also makes the stress of the vessel material higher. However the equivalent (von-Mises) stresses obtained from all of the simulation are still below the yield strength of the AHR vessel material so that the integrity of the vessel is maintained. (author)
Original Title
Kajian keselamatan material bejana Aqueous Homogeneous Reactor (AHR) dengan menggunakan program ANSYS
Primary Subject
Source
Budi Rohman; Liliana Yetta Pandi; Syahrir; Azhar; Ishak (BAPETEN, Jakarta (Indonesia)) (eds.); M Subekti (ed.) (BATAN, Jakarta (Indonesia)); Djarwani (ed.) (UI, Depok (Indonesia)); Zaki Suud (ed.) (ITB, Bandung (Indonesia)); Sihana (ed.) (UGM, Yogyakarta (Indonesia)); Nuclear Energy Regulatory Agency, Jakarta (Indonesia); [202 p.]; ISSN 1412-3258;
; Aug 2015; p. 58-62; Nuclear safety seminar 2015; Seminar keselamatan nuklir 2015; Jakarta (Indonesia); 13 Aug 2015; Also available from Center for Utilization of Informatics and Region Strategic Nuclear, National Nuclear Energy Agency, Puspiptek Area, Fax. 62-21-7560895, Serpong, Tangerang Selatan 15314 (ID); 11 refs.; 2 tabs.; 4 figs.

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BETA DECAY RADIOISOTOPES, BETA-MINUS DECAY RADIOISOTOPES, CONTAINERS, DAYS LIVING RADIOISOTOPES, EVEN-ODD NUCLEI, FLUID FUELED REACTORS, HOMOGENEOUS REACTORS, INTERMEDIATE MASS NUCLEI, ISOTOPES, LIQUID HOMOGENEOUS REACTORS, MOLYBDENUM ISOTOPES, NUCLEI, RADIOISOTOPES, REACTORS, SAFETY, SIMULATION, WATER COOLED REACTORS, WATER MODERATED REACTORS
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AbstractAbstract
No abstract available
Original Title
Einweg-Kugelhaufenreaktor zur Elektrizitaetserzeugung
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1 fig.; 2 tabs.; 6 refs.
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Journal Article
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Atomwirtsch., Atomtech; v. 17(9/10); p. 518-519
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AbstractAbstract
[en] In Mexico there is one operational research reactor, a 1 MW TRIGA reactor, and one operational subcritical facility. Another reactor, a SUR-100 homogeneous reactor, was decommissioned after shutdown in 1984, and another subcritical facility is in the condition of 'shut down'. A brief description of these reactors is given
Primary Subject
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International Atomic Energy Agency, Nuclear Fuel Cycle and Materials Section, Vienna (Austria); 88 p; ISBN 92-0-109006-4;
; ISSN 1011-4289;
; Jun 2006; p. 71-74; Also available on-line: http://www-pub.iaea.org/MTCD/publications/PDF/te_1508_web.pdf; For availability on CD-ROM, please contact IAEA, Sales and Promotion Unit, E-mail: sales.publications@iaea.org; Web site: http://www-pub.iaea.org/MTCD/publications.asp; Figs


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