Use of molybdenum as a structural material of fuel elements for improving nuclear reactors safety
-
A. N. Shmelev
Abstract
Main purpose of the study is justifying the use of molybdenum as a structural material of fuel elements for improving the safety of nuclear reactors. Particularity of the used molybdenum is that its isotopic composition corresponds to molybdenum, which is obtained as tailing during operation of the separation cascade for producing a material for medical diagnostics of cancer. The following results were obtained: A method for reducing the thermal constant of fuel elements for light water and fast reactors by using dispersion fuel in cylindrical fuel rods containing, for example, granules of metallic U-Mo-alloy into Mo-matrix was proposed; the necessity of molybdenum enrichment by weakly absorbing isotopes was shown; total use of isotopic molybdenum will be more than 50 %.
Kurzfassung
Hauptziel der Studie ist es, die Verwendung von Molybdän als Strukturmaterial von Brennelementen zur Verbesserung der Sicherheit von Kernreaktoren zu rechtfertigen. Besonderheit des verwendeten Molybdäns ist, dass seine Isotopenzusammensetzung der entspricht, die als Abraum bei der Trennkaskade zur Herstellung von Ausgangsstoffen für die medizinische Krebsdiagnostik erzeugt wird. Folgende Ergebnisse wurden erhalten: das vorgeschlagene Verfahren reduziert die Zeitkonstante der Brennelemente für Leichtwasserreaktoren und schnelle Reaktoren durch Verwendung des Dispersionsbrennstoffs in zylindrischen Brennelementen, die beispielsweise Granulate von metallischen U-Mo-Legierung im Mo-Gefüge enthalten; die Notwendigkeit der Molybdän-Anreicherung schwach absorbierender Isotope wurde gezeigt; isotopes Molybdän wird zu mehr als 50 % verwendet.
References
1 Hummel, H. H.; Okrent, D.: Reactivity Coefficients in Large Fast Power Reactors. La Grange Park, Illinois, American Nuclear Society, 1970Search in Google Scholar
2 Kalin, B. A.; Platonov, P. A.; Tuzov, Yu. V.; Chernov, I. I.; Shtrombakh, Ya. I.: Fizicheskoe materialovedenie: Uchebnik dlya vuzov, Vol. 6, Konstruktcionnye materialy yadernoy tekhniki, NRNU MEPhI, Moscow, 2012Search in Google Scholar
3 Grigor'ev, I. S.; Meylikhov, E. Z.: Fizicheskie velichiny: Spravochnik. Energoatomizdat, Moscow, 1991Search in Google Scholar
4 Smirnov, A. Yu.; Sulaberidze, G. A.: Sravnenie sposobov obogascheniya promezshutochnykh komponentov v kaskadakh iz odinakovogo chisla razdelitel'nykh komponentov. Atomnaya energiya117 (2014) 274–279Search in Google Scholar
5 Baranov, V. G.; Godin, Yu. G.; Tenishev, A. V.; Khlunov;A. V., Novikov;V. V.: Fizicheskoe materialovedenie: Uchebnik dlya vuzov. Pod obschey red. Kalina B.A., Vol. 7, Yadernye toplivnye materialy, NRNU MEPhI, Moscow, 2012Search in Google Scholar
6 Dolgov, A. B.; Novikov, V. V.; Ivanov, A. S.: Novoye toplivo dlya VVER. Atomniy ekspert6–7 (2013) 30–34Search in Google Scholar
7 Sorokin, A. P.; KalyakinS.G.; KozlovF.A.: Visokotemperaturnaya yadernaya energotekhnologiya na osnove bistrikh reaktorov s natrievim teplonositelem dlya proizvodstva vodoroda. Atomnaya energiya116 (2014) 194–283Search in Google Scholar
8 Gromov, B. F.; Demishonkov, A. P.; Toshinskiy, G. I.: Sposob zaschity konstruktcionnykh materialov ot korrozii pri povyshennykh temperaturakh v zhidkom svintce, vismute i ikh splavakh. Patent of Russian Federation, No. 2066710, Class C23F 11/00, Date of filing 10.03.1993Search in Google Scholar
9 Shornikov, D. P.: Distinctive Features of Interaction of the U-Mo Fuel Composition Fission Products and the Al Matrix with Barrier Coating. Proc. of the 12th International Conference on Research Reactor Fuel Management (2008) 26–29Search in Google Scholar
10 Shmelev, A. N., Kulikov, G. G., Kulikov, E. G., Apse, V. A.: O potentciale gibridnykh (sintez-delenie) narabotchikov topliva dlya yadernykh reactorov: stabilizirovannye razmnozhayuschie svoystva, glubokoe vygoranie, zaschischennoe toplivo, NRNU MEPhI, Moscow, 2014Search in Google Scholar
© 2016, Carl Hanser Verlag, München
Articles in the same Issue
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- Use of molybdenum as a structural material of fuel elements for improving nuclear reactors safety
- Effect of ultra high temperature ceramics as fuel cladding materials on the nuclear reactor performance by SERPENT Monte Carlo code
- Spatial distribution of nanoparticles in PWR nanofluid coolant subjected to local nucleate boiling
- Impact of mesh points number on the accuracy of deterministic calculations of control rods worth for Tehran research reactor
- Dependence of neutron rate production with accelerator beam profile and energy range in an ADS-TRIGA RC1 reactor
- Effects of the wallpaper fuel design on the neutronic behavior of the HTR-10
- Loss of flow Accident (LOFA) analyses using LabView-based NRR simulator
- Basket criticality design of a dual purpose cask for VVER 1000 spent fuel assemblies
- Simulation of polycarbonate-CNT nanocomposite dosimeter based on electrical characteristics
- Thermoluminescence properties of micro and nano structure hydroxyapatite after gamma irradiation
- Equilibrium based analytical model for estimation of pressure magnification during deflagration of hydrogen air mixtures
- Polynomial approach method to solve the neutron point kinetics equations with use of the analytic continuation
- The slab albedo problem for the triplet scattering kernel with modified FN method
- Calculation of the fuel composition and the deterministic reloading pattern in the second cycle of the BUSHEHR VVER-1000 reactor using the weighting factor method
Articles in the same Issue
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- Use of molybdenum as a structural material of fuel elements for improving nuclear reactors safety
- Effect of ultra high temperature ceramics as fuel cladding materials on the nuclear reactor performance by SERPENT Monte Carlo code
- Spatial distribution of nanoparticles in PWR nanofluid coolant subjected to local nucleate boiling
- Impact of mesh points number on the accuracy of deterministic calculations of control rods worth for Tehran research reactor
- Dependence of neutron rate production with accelerator beam profile and energy range in an ADS-TRIGA RC1 reactor
- Effects of the wallpaper fuel design on the neutronic behavior of the HTR-10
- Loss of flow Accident (LOFA) analyses using LabView-based NRR simulator
- Basket criticality design of a dual purpose cask for VVER 1000 spent fuel assemblies
- Simulation of polycarbonate-CNT nanocomposite dosimeter based on electrical characteristics
- Thermoluminescence properties of micro and nano structure hydroxyapatite after gamma irradiation
- Equilibrium based analytical model for estimation of pressure magnification during deflagration of hydrogen air mixtures
- Polynomial approach method to solve the neutron point kinetics equations with use of the analytic continuation
- The slab albedo problem for the triplet scattering kernel with modified FN method
- Calculation of the fuel composition and the deterministic reloading pattern in the second cycle of the BUSHEHR VVER-1000 reactor using the weighting factor method
