Problems of Long Term and Safe Storage of Unloaded and Non-Unloaded Spent Nuclear Fuel for Nuclear Submarines with Liquid-Metal Coolant

2003 ◽  
pp. 341-348 ◽  
Author(s):  
D. Pankratov ◽  
V. Andreyanov ◽  
M. Bugrevev ◽  
A. Dedoul ◽  
Ye. Efimov ◽  
...  
Keyword(s):  
Liquid Metal ◽  
Nuclear Fuel ◽  
Spent Nuclear Fuel ◽  
Liquid Metal Coolant ◽  
Safe Storage ◽  
Metal Coolant

Assimilation of a Closed Uranium-Plutonium Nuclear Fuel Cycle Based on Fast Reactors With Liquid-Metal Coolant

Atomic Energy ◽  
2013 ◽  
Vol 115 (2) ◽  
pp. 78-82
Author(s):  
M. V. Radchenko ◽  
A. Yu. Shadrin ◽  
P. P. Poluektov ◽  
O. V. Shmidt ◽  
A. A. Tuzov
Keyword(s):  
Liquid Metal ◽  
Nuclear Fuel ◽  
Fuel Cycle ◽  
Nuclear Fuel Cycle ◽  
Fast Reactors ◽  
Liquid Metal Coolant ◽  
Uranium Plutonium ◽  
Metal Coolant

Modeling of Gas-Phase Transport in Heavy Liquid-Metal Coolant Flow in the HYDRA-IBRAE/LM Thermohydraulic Code

Atomic Energy ◽  
2021 ◽  
Vol 129 (3) ◽  
pp. 127-134
Author(s):  
V. M. Alipchenkov ◽  
Ya. V. Grudtsyn ◽  
N. A. Mosunova
Keyword(s):  
Liquid Metal ◽  
Gas Phase ◽  
Coolant Flow ◽  
Heavy Liquid ◽  
Liquid Metal Coolant ◽  
Gas Phase Transport ◽  
Phase Transport ◽  
Metal Coolant

Modeling the flow of liquid-metal coolant in the T-shaped mixer

2016 ◽  
Vol 23 (3) ◽  
pp. 379-382
Author(s):  
O. N. Kashinsky ◽  
P. D. Lobanov ◽  
A. S. Kurdyumov ◽  
N. A. Pribaturin
Keyword(s):  
Liquid Metal ◽  
Liquid Metal Coolant ◽  
Metal Coolant

Recent Advancement on Liquid Metal Cooling for Thermal Management of Computer Chip

2010 ◽  
Author(s):  
Jing Liu ◽  
Yue-Guang Deng ◽  
Zhong-Shan Deng
Keyword(s):  
Liquid Metal ◽  
Thermal Management ◽  
New Technology ◽  
Air Cooling ◽  
Liquid Metal Coolant ◽  
Cooling Device ◽  
Chip Cooling ◽  
Cooling Method ◽  
Liquid Metal Cooling ◽  
Metal Coolant

Efficient cooling of a high performance computer chip has been an extremely important however becoming more and more tough issue. The recently invented liquid metal cooling method is expected to pave the way for high flux heat dissipation which is hard to tackle otherwise by many existing conventional cooling strategies. However, as a new thermal management method, its application also raised quite a few challenging fundamental and practical issues for solving. To illustrate the development of the new technology, this talk is dedicated to present an overview on the latest advancements made in the author’s lab in developing the new generation chip cooling device based on the liquid metal coolant with melting point around room temperature. The designing and optimization of the cooling device and component will be discussed. Several major barriers to prevent the new method from practical application such as erosion between liquid metal coolant and its substrate material will be outlined with good solutions clarified. Performance comparison between the new chip cooling method with commercially available products with highest quality such as air cooling, water cooling and heat pipe cooling devices were evaluated. Typical examples of using liquid metal cooling for the thermal management of a real PC or even super computer will be demonstrated. Further, miniaturizations on the prototype device by extending it as a MEMS cooling device or mini/micro channel liquid metal cooling device will also be explained. Along with the development of the hardware, some fundamental heat transfer issues in characterizing the liquid metal cooling device will be discussed through numerical or analytical model. Future challenging issues in pushing the new technology into large scale practices will be raised. From all the outputs obtained so far, it can be clearly seen that the new cooling strategy will find very promising and significant applications in a wide variety of engineering situations whenever thermal managements or heat transport are needed.

scholarly journals Decay heat power of spent nuclear fuel of power reactors with high burnup at long-term storage

2017 ◽  
Vol 153 ◽  
pp. 07035 ◽  
Author(s):  
Mikhail Ternovykh ◽  
Georgy Tikhomirov ◽  
Ivan Saldikov ◽  
Alexander Gerasimov
Keyword(s):  
Nuclear Fuel ◽  
Spent Nuclear Fuel ◽  
Heat Power ◽  
Decay Heat ◽  
Long Term Storage ◽  
High Burnup ◽  
Term Storage

Dissolution of spent nuclear fuel fragments at high alkaline conditions under H2 overpressure

MRS Advances ◽  
2016 ◽  
Vol 1 (62) ◽  
pp. 4163-4168
Author(s):  
E. González-Robles ◽  
M. Herm ◽  
V. Montoya ◽  
N. Müller ◽  
B. Kienzler ◽  
...  
Keyword(s):  
Aqueous Solution ◽  
Partial Pressure ◽  
Nuclear Fuel ◽  
Alkaline Solution ◽  
Spent Nuclear Fuel ◽  
Dissolution Tests ◽  
The Matrix ◽  
Alkaline Conditions ◽  
Long Term Behavior

ABSTRACTThe long-term behavior of the UO2 fuel matrix under conditions of the Belgian “Supercontainer design” was investigated by dissolution tests of high burn-up spent nuclear fuel (SNF) in high alkaline solution under 40 bar of (Ar + 8%H2) atmosphere. Four fragments of SNF, obtained from a pellet previously leached during two years, were exposed to young cement water with Ca (YCWCa) under 3.2 bar H2 partial pressure in four single/independent autoclave experiments for a period of 59, 182, 252 and 341 days, respectively. After a decrease of the concentration of dissolved 238U, which is associated with a reduction of U(VI) to U(IV), the concentration of 238U in solution is constant in the experiments running for 252 and 341 days. These observations indicate an inhibition of the matrix dissolution due to the presence of H2. A slight increase in the concentration of 90Sr and 137Cs in the aqueous solution indicates that there is still dissolution of the grain boundaries. These findings are similar to those reported for spent nuclear fuel corrosion in synthetic near neutral pH solutions.

Formation of the Structure of a Eutectic Alloy of the Nb – Si System During Directed Crystallization with Liquid-Metal Coolant

2017 ◽  
Vol 59 (7-8) ◽  
pp. 513-517
Author(s):  
Yu. A. Bondarenko ◽  
A. B. Echin ◽  
M. Yu. Kolodyazhnyi ◽  
V. A. Surova
Keyword(s):  
Liquid Metal ◽  
Eutectic Alloy ◽  
Directed Crystallization ◽  
Liquid Metal Coolant ◽  
Metal Coolant

Using of optimization geometric design methods for the problems of the spent nuclear fuel safe storage

2020 ◽  
Vol 25 (3) ◽  
pp. 51-63
Author(s):  
Chugay A.M. ◽  
◽  
Alyokhina S.V. ◽  
Keyword(s):  
Mathematical Model ◽  
Nonlinear Programming ◽  
Nuclear Fuel ◽  
Site Selection ◽  
Spent Nuclear Fuel ◽  
Optimal Placement ◽  
Storage Site ◽  
Safe Storage ◽  
Geometric Objects ◽  
Technological Limitations

Packing optimization problems have a wide spectrum of real-word applications. One of the applications of the problems is problem of placement of containers with spent nuclear fuel (SNF) on the storage platform. The solution of the problem can be reduced to the solution of the problem of finding the optimal placement of a given set of congruent circles into a multiconnected domain taking into account technological restrictions. A mathematical model of the prob-lem is constructed and its peculiarities are considered. Our approach is based on the mathematical modelling of rela-tions between geometric objects by means of phi-function technique. That allowed us to reduce the problem solving to nonlinear programming. Today, an important scientific problem is the problem of creating conditions for safe storage of spent nuclear fuel. In the process of creating any dry spent nuclear fuel storage, the following main stages can be identified: site selection, storage design, construction, operation and decommissioning. A full check for compliance of the repository and its elements with these standards usually begins at the design stage. At the stage of site selection, the inspection for compliance with safety standards is carried out only in terms of the impact of the repository as a whole on the environment. This approach cannot be considered fully appropriate, because, taking into account, for example, all the climatic features of the future storage site, it is possible to adjust the thermal storage regimes of spent nuclear fuel. Similarly, it can be considered necessary to analyze and select the shape of the storage site in order to accommo-date the maximum possible number of spent fuel containers. Such a choice, obviously, should be made taking into ac-count the norms of nuclear, radiation and thermal safety, as well as in compliance with technological limitations. The problem of finding the optimal placement of containers taking into account the given technological limitations can be formulated in the form of the problem of optimization of geometric design. Therefore, the purpose of the study is to build a mathematical model of the problem and study its characteristics to develop effective methods of solution. The proposed approach is based on mathematical modeling of relations between geometric objects using the method of phi-functions. This allowed to reduce the solution of the problem to the problem of nonlinear programming.

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