Working-life and friction of fuel assemblies in water-cooled, water-moderated power reactors
Dragunov, Y. G.; Makarov, V. V.; Drozdov, Y. N.
German National Library of Science and Technology (GetInfo) (German)
Water and Regolith Shielding for Surface Reactor Missions
Poston, David I.; Leichliter, Katrina J.; Dixon, David D.
U–Zr–Fe–O Melt density
Diakov, E.; Tsurikov, D.; Zagryazkin, V.
Uranium target for electron accelerator based neutron source for BNCT
Kennedy, K.; Nigg, D. W.; Collens, T. J.
Upgrading water-conditioning units at nuclear power plants with water-moderated reactors
Goncharuk, V. V.; Voloshina, A. M.; Strakhov, B. E.
Thermal-hydraulic instabilities in pressure tube graphite-moderated boiling water reactors
Tsiklauri, G.; Schmitt, B.; Department of Energy, Washington, DC
Thermal-Hydraulic Instabilities in Pressure Tube Graphite-Moderated Boiling Water Reactors
Tsiklauri, G.; Schmitt, B.; ANS
Thermal and Radiation Characteristics of Hydrazine in the Primary Loop of Nuclear Power Plants with Water-Cooled, Water-Moderated Reactors
Arkhipov, O. P.; Bugaenko, V. L.; Kabakchi, S. A.
The canadian research reactors and their uses
W B Lewis
The United Kingdom research reactors and their uses
F W Fenning
The United Kingdom Atomic Energy Authority and its functions
Sir John Cockcroft
The Third Generation of Heavy-Water Moderated Reactors
Popov, A.V.; Marleau, G.; Olekhnovitch, A.
Supercritical water cooled reactors
Studying helium accumulation in austenitic steels for evaluating radiation damage in internals of water-moderated water-cooled power reactors
Belozerov, S. V.; Neustroyev, V. S.; Shamardin, V. K.
Shamardin, V.; Belozerov, S.; Neustroyev, V.
Status and prospects for pressure-tube water-cooled graphite-moderated reactors
Adamov, E. O.; Grozdov, I. I.; Petrov, A. A.
Some Problems of Large Scale Safety Test Stands
Smolin, V. N.; Shishov, V. P.; Ionov, A. I.
Simulation of Thermal Breakdown of a Reactor Vessel as a Result of Heavy Accident in a Nuclear Power Plant with Reactors of VVER (Water-moderated Water-cooled Power Reactor) Type
Dolgov, V. V.; Kashcheev, M. V.; Muranov, Y. V.
Safety considerations affecting the design and instalation of water-cooled and water-moderated reactors on merchant ships
Society of Naval Architects and Marine Engineers / Atomic Energy Panel
Research reactors : light water moderated ... ; light water and oil moderated ... ; heavy water moderated ... ; graphite moderated
United States / Atomic Energy Commission
Reactor Physics Methods for Design and Analysis of Heavy Water Moderated Reactors
Srinivasan, K. R.; Indian Society for Radiation Physics; Kalpakkam Chapter
Reactivity feedback and control margins in natural uranium fueled and heavy water moderated nuclear research reactors
Khan, M. J.; Ahmad, N.
Raising the Efficiency of Evacuating the Corrosion Products from the Primary Coolant Circuits of Water-Moderated Reactors (VVR) by Standard Decontaminating Filters
Orlenkov, I. S.; Krasnoperov, V. M.; Gusev, B. A.
Preliminary Thermomechanical Loading (Warm Prestressing) as a Promising Method for Increasing the Radiation Resistance of the Vessels of Water-Moderated Water-Cooled Power Reactors Operating under High Pressure
Pokrovskii, V. V.; Kaplunenko, V. G.; Fedorov, V. G.
Possibility, admissability, and desirability of implementing pulsed stochastic regimes in boiling-water reactors with natural coolant circulation
Possibility of developing low-power reactors with a pebble-bed core
Sikorin, S.; Mikhalevich, A.; Akhramovich, A.
Positron study of radiation embrittlement of steels used in water cooled, water moderated energy reactors
Slugen, V.; Zeman, A.; Petriska, M.
Plutonium Production and Excess Reactivities in Natural Uranium Fueled and Heavy Water Moderated Reactors
Malkawi, A. S. R.; Ahmad, N.; Khan, L. A.
P16P1262 : The Third Generation of Heavy-Water Moderated Reactors
Optimization of the Materials Composition in External Core Catchers for Nuclear Reactors
Traktuev, O. M.; Vlasov, A. S.; Mineev, V. N.
Neutronics analyses of natural uranium fueled, light water cooled, heavy water moderated and graphite reflected nuclear reactors
Khan, M. J.; Ahmad, N.
Neutronic performance of high-density LEU fuels in water-moderated and water-reflected research reactors
Bretscher, M. M.; Matos, J. E.; Department of Energy, Washington, DC
Monitoring, diagnostics, and control system for large-capacity nuclear power facilities with water moderated and cooled reactors
Kalinushkin, A.; Mitin, V.; Kozlov, V.
Modifications to MELCOR for the analysis of heavy-water moderated, U-A1 fuel reactors
Church, J. P.; Leonard, M. T.; Williams, K. A.
Moderator temperature effect on reactivity in light water moderated experimental reactors
Mohapatra, D. K.; Mohanakrishnan, P.
Metastability of structure and radiation resistance of nickel-chromium alloys
Votinov, S.; Kolotushkin, V.
MODERATOR WORTH AND REACTIVITY CONTROL IN HEAVY WATER MODERATED NATURAL URANIUM FUELED REACTORS
Khan, M. J.; Aslam; Ahmad, N.
LEAKAGE REACTIVITY PENALTY AND CORE BURNUP OF NATURAL URANIUM FUELED AND HEAVY WATER MODERATED REACTORS
Izmenenie geometričeskich parametrov tvėlov vodo-vodjanych ėnergetičeskich reaktorov pri ėkspluatacii do vygoranija 50 MWt-sut/kg urana
Žitelev, V. A.
Innovative development of nuclear power in Russia
Solonin, M.; Zrodnikov, A.; Asmolov, V.
Hydrodynamic load impact on vibrations of fuel element clusters in water-moderated water-cooled power reactor (VVER) fuel assemblies
Solonin, V.; Perevezentsev, V.
Heavy Water Moderated Reactors Advances and Challenges
Meneley, D. A.; Olmstead, R. A.; Yu, A. M.
Handling spent nuclear fuel and radioactive wastes on the shore servicing base in Gremikha
Pavlov, V.; Samarin, E.; Papkovskii, B.
Fuel utilization in VVÉR-1000: Status and prospects
Spirkin, E.; Pavlov, V.; Novikov, A.
Experimental and Analytical Study on Thermal Hydraulics in Reduced Moderated Water Reactors
Akimoto, H.; Japan Atomic Energy Research Institute
Experience in Developing the Simulators of Fuel Rods of Water-Moderated Reactors
Balashov, S. M.; Boltenko, E. A.; Vinogradov, V. A.
Evolution of the structure of the WWER-1000 reactor vessel from the prototype model to WWER-1200
Bakaldin, V.; Fedosov, V.; Petrov, V.
Effect of friction forces on efficiency and life of fuel assemblies of water-moderated reactors
Dragunov, Y. G.; Drozdov, Y. N.; Makarov, V. V.
EFFECTS OF MODERATION LEVEL ON CORE REACTIVITY AND NEUTRON FLUXES IN NATURAL URANIUM FUELED AND HEAVY WATER MODERATED REACTORS
Khan, M. J.; Aslam; Ahmad, N.
EFFECTS OF GRAPHITE REFLECTOR ON THE REACTIVITY OF NATURAL URANIUM FUELED AND HEAVY WATER MODERATED RESEARCH REACTORS
Development of safeguards procedures for heavy water moderated, cooled and reflected pressurised water type reactors
Institut für Angewandte Reaktorphysik < Karlsruhe>
Development of a standard for the moderator temperature coefficient of reactivity in water-moderated power reactors
Mosteller, R. D.; Department of Energy, Washington, DC
Development of a Standard for Calculation and Measurement of the Moderator Temperature Coefficient of Reactivity in Water-Moderated Power Reactors
Mosteller, R. D.; Apperson, C. E.; Gavin, P. H.
Development of a Silicon Calorimeter for Dosimetry Applications in a Water-Moderated Reactor
Luker, S.M.; Griffin, P.J.; DePriest, K.R.
Density-wave Instability with Neutronic-Coupling in a Natural Circulation Heavy Water Moderated Boiling Light Water Cooled Pressure Tube Type Reactor
Nayak, A. K.; Aritomi, M.; Raj, V. V.
Damage to heat exchanger tubes in steam generators on nuclear power stations with water-moderated water-cooled reactors
Titov, V. F.; Banyuk, G. F.; Brykov, S. I.
Criticality Studies of a Natural Uranium Fueled, Light Water Cooled and Heavy Water Moderated Nuclear Reactors
Malkawi, S. R.; Ahmad, A.; Nasir, A.
Core and Plant Design of the Power Reactor Cooled and Moderated by Supercritical Light Water
Dobashi, K.; Oka, Y.; Koshizuka, S.
Control of Power Distribution in Water-Moderated Water-Cooled Power Reactors by Means of Offset-Offset Diagram
Filimonov, P. E.
Filimonov, P. E.
Chemistry in water moderated/cooled nuclear reactors: the primary system
Can thorium compete with uranium ? : an assessment for heavy-water and graphite moderated reactors
Calculation of the moderator temperature coefficient of reactivity for water moderated reactors
Mourtzanos, K.; Housiadas, C.; Antonopoulos-Domis, M.
Bulgarian experience on calculation of burnable absorbers in water-cooled and -moderated reactors -(VVER)
Prodanova, R.; Apostolov, T.; Yugoslav Nuclear Society
BN-800 as a New Stage in the Development of Fast Sodium-Cooled Reactors
Matveev, V. I.; Chebeskov, A. N.; Poplavskii, V. M.
Application of the system of automated monitoring of the residual service life for the solution of the problems of operation of nuclear power plants with water-cooled water-moderated reactors
Berkovich, V. Y.; Bogachev, A. V.; Dranchenko, B. N.
Berkovich, V.; Bogachev, A.; Dranchenko, B.
Analytical investigations of transitional operating modes of the second circuit of units at NPP with water-moderated reactors with consideration of control systems
Pikin, M. A.; Nesterov, Y. V.
Pikin, M.; Nesterov, Yu.
Analysis of the events of failures of pipelines made of austenitic steel in nuclear power-generating industry
Timofeev, B.; Karzov, G.; Chernaenko, T.
An efficient analytical form for the period-reactivity relation of beryllium and heavy-water moderated reactors
Aboanber, A. E.
A school investigation into Chernobyl fallout
R D Plant
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