scholarly journals Alternative fuel cycle options: performance characteristics and impact on nuclear power growth potential

1977 ◽  
Author(s):  
Y. I. Chang ◽  
C. E. Till ◽  
R. R. Rudolph ◽  
J. R. Deen ◽  
M. J. King
Keyword(s):  
Nuclear Power ◽  
Fuel Cycle ◽  
Alternative Fuel ◽  
Performance Characteristics ◽  
Growth Potential ◽  
Power Growth

2. The Salzburg Conference on Nuclear Power and its Fuel Cycle

1978 ◽  
Vol 2 (2) ◽  
pp. 196-199
Author(s):  
R. KRYMM
Keyword(s):  
Nuclear Power ◽  
Fuel Cycle

Nuclear Power in Latin America: An Overview of Its Present Status

1983 ◽  
Vol 25 (3) ◽  
pp. 377-415 ◽  
Author(s):  
Margarete K. Luddemann
Keyword(s):  
Developing Countries ◽  
Latin America ◽  
Nuclear Power ◽  
Nuclear Energy ◽  
Fuel Cycle ◽  
Field Studies ◽  
Energy Agency ◽  
Self Sufficiency ◽  
Policy Concern ◽  
Alternative Sources

The pivotal role energy plays in national economics not only converts the access to sources of supply into a vivid issue of foreign policy concern, but also causes an understandable preoccupation with investment capabilities and self-sufficiency. A report prepared by the International Atomic Energy Agency (IAEA) in 1974 predicted a bright future for nuclear energy in the i developing countries and encouraged use of this form of energy after numerous field studies.A nation that commits itself to nuclear energy by purchasing nuclear power-generating technology but not fuel cycle facilities incurs the risk of becoming dependent upon the supplier country because a quick switch to alternative sources of supply is difficult in cases of curtailment of fuel.

scholarly journals PRELIMINARY DESIGN OF RDE FEEDWATER PUMP IMPELLER

2018 ◽  
Vol 20 (1) ◽  
pp. 1 ◽  
Author(s):  
Sri Sudadiyo
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Reactor ◽  
Thermal Power ◽  
Performance Characteristics ◽  
Preliminary Design ◽  
Triangle Diagram ◽  
Pump Impeller ◽  
Impeller Blade ◽  
Feedwater Pump

Nowadays, pumps are being widely used in the thermal power generation including nuclear power plants. Reaktor Daya Eksperimental (RDE) is a proposed nuclear reactor concept for the type of nuclear power plant in Indonesia. This RDE has thermal power 10 MWth, and uses a feedwater pump within its steam cycle. The performance of feedwater pump depends on size and geometry of impeller model, such as the number of blades and the blade angle. The purpose of this study is to perform a preliminary design on an impeller of feedwater pump for RDE and to simulate its performance characteristics. The Fortran code is used as an aid in data calculation in order to rapidly compute the blade shape of feedwater pump impeller, particularly for a RDE case. The calculations analyses is solved by utilizing empirical correlations, which are related to size and geometry of a pump impeller model, while performance characteristics analysis is done based on velocity triangle diagram. The effect of leakage, pass through the impeller due to the required clearances between the feedwater pump impeller and the volute channel, is also considered. Comparison between the feedwater pump of HTR-10 and of RDE shows similarity in the trend line of curve shape. These characteristics curves will be very useful for the values prediction of performance of a RDE feedwater pump. Preliminary design of feedwater pump provides the size and geometry of impeller blade model with 5-blades, inlet angle 14.5 degrees, exit angle 25 degrees, inside diameter 81.3 mm, exit diameter 275.2 mm, thickness 4.7 mm, and height 14.1 mm. In addition, the optimal values of performance characteristics were obtained when flow capacity was 4.8 kg/s, fluid head was 29.1 m, shaft mechanical power was 2.64 kW, and efficiency was 52 % at rotational speed 1750 rpm.Keywords: Blade, impeller, pump, RDEDESAIN AWAL IMPELER POMPA AIR UMPAN RDE. Saat ini, pompa digunakan secara luas dalam pembangkit tenaga termal termasuk pembangkit listrik tenaga nuklir. Reaktor Daya Eksperimental (RDE) merupakan konsep reaktor nuklir yang diusulkan untuk tipe PLTN di Indonesia. RDE ini memiliki daya termal 10 MWth, dan menggunakan pompa air umpan dalam siklus uapnya. Kinerja pompa air umpan bergantung pada ukuran dan geometri model impeller, seperti jumlah sudu dan sudut sudu. Tujuan dari penelitian ini adalah untuk membuat rancangan awal impeller pompa air umpan untuk RDE dan untuk mensimulasikan karakteristik kinerjanya. Kode Fortran digunakan sebagai bantuan dalam penghitungan data untuk untuk mengkalkulasi secara cepat bentuk sudu impeller pompa air umpan, terutama pada kasus RDE. Analisis perhitungan dipecahkan menggunakan korelasi empiris yang terkait dengan ukuran dan geometri model impeller pompa, sedangkan analisis karakteristik kinerja dilakukan berdasarkan diagram segitiga kecepatan. Pengaruh bocoran, melalui impeler akibat celah yang diperlukan antara impeller pompa air umpan dan saluran volute, juga dipertimbangkan. Perbandingan antara pompa air umpan HTR-10 dan RDE menunjukkan kemiripan dalam garis tren bentuk kurva. Kurva karakteristik ini akan sangat berguna untuk perkiraan nilai kinerja pompa air umpan RDE. Desain awal pompa air umpan memberikan ukuran dan geometri model sudu impeller dengan 5-sudu, sudut masuk 14,5 derajat, sudut keluar 25 derajat, diameter dalam 81,3 mm, diameter luar 275,2 mm, ketebalan 4,7 mm, dan tinggi 14,1 mm. Selain itu, nilai optimal karakteristik kinerja diperoleh ketika kapasitas aliran 4,8 kg/s, head fluida 29,1 m, tenaga mekanik poros 2,64 kW, dan efisiensi 52 % pada kecepatan putaran 1750 rpm.Kata kunci: Sudu, impeler, pompa, RDE

scholarly journals THE ADMISSIBILITY OF THE CLOSED FUEL CYCLE OF NUCLEAR POWER ENGINEERING

2021 ◽  
Vol 44 (1) ◽  
pp. 5-12
Author(s):  
E.P. Velikhov ◽  
◽  
A.O. Gol’tsev ◽  
V.D. Davidenko ◽  
A.V. El’shin ◽  
...  
Keyword(s):  
Nuclear Power ◽  
Fuel Cycle ◽  
Nuclear Power Engineering ◽  
Power Engineering ◽  
Closed Fuel Cycle

scholarly journals Small nuclear power plants for power supply in arctic regions: assessment of spent nuclear fuel radioactivity

2018 ◽  
Vol 4 (2) ◽  
pp. 119-125
Author(s):  
Vadim Naumov ◽  
Sergey Gusak ◽  
Andrey Naumov
Keyword(s):  
Nuclear Fuel ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Fuel Cycle ◽  
Mass Composition ◽  
Published Data ◽  
Pressurized Water ◽  
Fuel Cycles ◽  
Reactor Cores

The purpose of the present study is the investigation of mass composition of long-lived radionuclides accumulated in the fuel cycle of small nuclear power plants (SNPP) as well as long-lived radioactivity of spent fuel of such reactors. Analysis was performed of the published data on the projects of SNPP with pressurized water-cooled reactors (LWR) and reactors cooled with Pb-Bi eutectics (SVBR). Information was obtained on the parameters of fuel cycle, design and materials of reactor cores, thermodynamic characteristics of coolants of the primary cooling circuit for reactor facilities of different types. Mathematical models of fuel cycles of the cores of reactors of ABV, KLT-40S, RITM-200M, UNITERM, SVBR-10 and SVBR-100 types were developed. The KRATER software was applied for mathematical modeling of the fuel cycles where spatial-energy distribution of neutron flux density is determined within multi-group diffusion approximation and heterogeneity of reactor cores is taken into account using albedo method within the reactor cell model. Calculation studies of kinetics of burnup of isotopes in the initial fuel load (235U, 238U) and accumulation of long-lived fission products (85Kr, 90Sr, 137Cs, 151Sm) and actinoids (238,239,240,241,242Pu, 236U, 237Np, 241Am, 244Cm) in the cores of the examined SNPP reactor facilities were performed. The obtained information allowed estimating radiation characteristics of irradiated nuclear fuel and implementing comparison of long-lived radioactivity of spent reactor fuel of the SNPPs under study and of their prototypes (nuclear propulsion reactors). The comparison performed allowed formulating the conclusion on the possibility in principle (from the viewpoint of radiation safety) of application of SNF handling technology used in prototype reactors in the transportation and technological process layouts of handling SNF of SNPP reactors.

scholarly journals DYNAMIC MODELING AND ANALYSIS OF ALTERNATIVE FUEL CYCLE SCENARIOS IN KOREA

2007 ◽  
Vol 39 (1) ◽  
pp. 85-94 ◽  
Author(s):  
Chang-Joon Jeong ◽  
Hang-Bok Choi
Keyword(s):  
Dynamic Modeling ◽  
Fuel Cycle ◽  
Alternative Fuel ◽  
Modeling And Analysis

Energy Waste and Nuclear Power Growth

1976 ◽  
Vol 32 (10) ◽  
pp. 18-21
Author(s):  
Frank von Hippel ◽  
Robert H. Williams
Keyword(s):  
Nuclear Power ◽  
Power Growth
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