Factors in the preliminary assessment of the economic effectiveness of an atomic fuel and power complex based on atomic power plants with fast reactors

1989 ◽  
Vol 67 (3) ◽  
pp. 625-628
Author(s):  
V. A. Tsykanov ◽  
G. I. Gadzhiev ◽  
E. V. Kirillov ◽  
O. V. Skiba ◽  
L. S. Demidova
Keyword(s):  
Power Plants ◽  
Economic Effectiveness ◽  
Fast Reactors ◽  
Preliminary Assessment ◽  
Power Complex ◽  
Atomic Power Plants

All-union Conference on the Preparation of Operating Personnel for Atomic Power Plants

1977 ◽  
Vol 42 (6) ◽  
pp. 587-588
Author(s):  
L. M. Voronin ◽  
G. N. Ushakov ◽  
V. M. Gordina
Keyword(s):  
Power Plants ◽  
Operating Personnel ◽  
Union Conference ◽  
Atomic Power Plants

Radiation safety of atomic power plants in the USSR

1983 ◽  
Vol 54 (4) ◽  
pp. 290-301
Author(s):  
E. I. Vorob'ev ◽  
L. A. Il'in ◽  
V. D. Turovskii ◽  
L. A. Buldakov ◽  
N. G. Gusev ◽  
...  
Keyword(s):  
Power Plants ◽  
Radiation Safety ◽  
Atomic Power Plants

scholarly journals On Capabilities and Limitations of Current Fast Neutron Flux Monitoring Instrumentation for the Demo LFR ALFRED

2016 ◽  
Vol 2 (4) ◽  
Author(s):  
Luigi Lepore ◽  
Romolo Remetti ◽  
Mauro Cappelli
Keyword(s):  
Monte Carlo ◽  
Neutron Flux ◽  
Fast Reactor ◽  
Nuclear Power ◽  
Power Plants ◽  
Fuel Cycle ◽  
Signal To Noise Ratio ◽  
Reactor Power ◽  
Fast Reactors ◽  
Flux Monitoring

Among GEN IV projects for future nuclear power plants, lead-cooled fast reactors (LFRs) seem to be a very interesting solution due to their benefits in terms of fuel cycle, coolant safety, and waste management. The novelty of this matter causes some open issues about coolant chemical aspects, structural aspects, monitoring instrumentation, etc. Particularly, hard neutron flux spectra would make traditional neutron instrumentation unfit to all reactor conditions, i.e., source, intermediate, and power range. Identification of new models of nuclear instrumentation specialized for LFR neutron flux monitoring asks for an accurate evaluation of the environment the sensor will work in. In this study, thermal hydraulics and chemical conditions for the LFR core environment will be assumed, as the neutron flux will be studied extensively by the Monte Carlo transport code MCNPX (Monte Carlo N-Particles X-version). The core coolant’s high temperature drastically reduces the candidate instrumentation because only some kinds of fission chambers and self-powered neutron detectors can be operated in such an environment. This work aims at evaluating the capabilities of the available instrumentation (usually designed and tailored for sodium-cooled fast reactors) when exposed to the neutron spectrum derived from the Advanced Lead Fast Reactor European Demonstrator, a pool-type LFR project to demonstrate the feasibility of this technology into the European framework. This paper shows that such a class of instrumentation does follow the power evolution, but is not completely suitable to detect the whole range of reactor power, due to excessive burnup, damages, or gamma interferences. Some improvements are possible to increase the signal-to-noise ratio by optimizing each instrument in the range of reactor power, so to get the best solution. The design of some new detectors is proposed here together with a possible approach for prototyping and testing them by a fast reactor.

Calculation of reactor water flow rate for purification of coolant in boiling-water single-loop atomic power plants

1980 ◽  
Vol 48 (1) ◽  
pp. 41-42
Author(s):  
V. V. Gerasimov ◽  
O. I. Martynova ◽  
O. T. Konovalova ◽  
T. I. Kosheleva
Keyword(s):  
Water Flow ◽  
Flow Rate ◽  
Power Plants ◽  
Water Flow Rate ◽  
Boiling Water ◽  
Single Loop ◽  
Reactor Water ◽  
Atomic Power Plants
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