JSC NIIEFA

Saint Petersburg, Russia

JSC NIIEFA

Saint Petersburg, Russia
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Khvostenko P.P.,RAS Research Center Kurchatov Institute | Anashkin I.O.,RAS Research Center Kurchatov Institute | Belyakov V.A.,JSC NIIEFA | Bondarchuk E.N.,JSC NIIEFA | And 3 more authors.
Fusion Engineering and Design | Year: 2017

Presently, the Tokamak T-15MD is being built in NRC "Kurchatov Institute", Russia. All elements of the magnet system have been manufactured by the end of 2015. The preassembly of the tokamak T-15MD magnet system is carried out at plant in Bryansk. The purpose of the preassembly of the magnet system is to bring together all of the elements, which will provide the necessary experience for the later assembly of the tokamak at the NRC "Kurchatov Institute" in Moscow. The results of the preassembly of the tokamak T-15MD magnet system are presented. © 2017 Elsevier B.V.


Alekseev A.B.,ITER Organization | Amoskov V.M.,JSC NIIEFA | Bazarov A.M.,JSC NIIEFA | Belov A.V.,JSC NIIEFA | And 7 more authors.
Fusion Engineering and Design | Year: 2017

The paper presents an attempt to proceed to a general concept of software environment for fast and consistent multi-task simulation of EM transients (engineering simulator for tokamak applications). As an example, the ITER tokamak is taken to introduce a computational technique. The strategy exploits parallel processing with optimized simulation algorithms based on using of influence functions and superposition principle to take full advantage of parallelism. The software has been tested on a multi-core supercomputer. The results were compared with data obtained in TYPHOON computations. A discrepancy was found to be below 0.4%. The computation cost for the simulator is proportional to the number of observation points. An average computation time with the simulator is found to be by hundreds times less than the time required to solve numerically a relevant system of differential equations for known software tools. © 2017 Elsevier B.V.


Alekseev A.,ITER Organization | Arslanova D.,JSC NIIEFA | Belyakov V.,Saint Petersburg State University | Bessette D.,ITER Organization | And 8 more authors.
Fusion Engineering and Design | Year: 2017

Active mitigation of pulsed heat load is foreseen for the ITER superconducting magnets during cyclic plasma scenarios to ensure stable operation of the cryoplant. The paper addresses a promising feedback control to smooth heat pulses in the primary cryogenic circuits of the ITER magnets. A feedback control signal is proposed that can be derived from direct measurements of helium parameters in a low pressure return cryoline to the cryoplant. Configurations with two or more LHe baths were investigated at the Auxiliary Cold Box (ACB) level. Efficiency of the proposed control approach was evaluated in thermohydraulic simulations. A possibility to control several cryogenic loops using a common regulator is demonstrated. © 2017 Elsevier B.V.


Minaev V.B.,RAS Ioffe Physical - Technical Institute | Gusev V.K.,RAS Ioffe Physical - Technical Institute | Sakharov N.V.,RAS Ioffe Physical - Technical Institute | Varfolomeev V.I.,RAS Ioffe Physical - Technical Institute | And 34 more authors.
Nuclear Fusion | Year: 2017

The Globus-M spherical tokamak has demonstrated practically all of the project objectives during the 15-year period of operation. The main factor limiting further progress in plasma performance is a relatively low toroidal magnetic field. The maximum toroidal magnetic field achieved on Globus-M was 0.4 T with the exception of a limited number of shots with 0.55 T, which led to damage of the toroidal field coil in 2002. The increase of the magnetic field up to 1.0 T together with the plasma current up to 0.5 MA will result in the significant enhancement of the operating parameters in the upgraded Globus-M2 machine. The experimental program will be focused on plasma heating and non-inductive current drive and will contribute to the creation of a physical and technological base for the compact fusion neutron source development. In the article a brief overview of the physical background for the machine upgrade is outlined. The current status of the project implementation is described. First experimental results on moderate magnetic field increase from 0.4 T up to 0.5 T in the existing Globus-M machine are discussed. The improvement of plasma confinement as well as enhancement of efficiency of the beam driven current is observed. © 2017 IAEA, Vienna.


Volodin A.,JSC NIIEFA | Kuznetcov V.,JSC NIIEFA | Davydov V.,JSC NIIEFA | Kokoulin A.,JSC NIIEFA | And 10 more authors.
Fusion Engineering and Design | Year: 2015

The current ITER design involves beryllium and tungsten as plasma facing materials for in-vessel components. Due to a high number of operating cycles and to the expected surface heat loads, thermal fatigue is one of the most damaging mechanisms for the plasma facing components (PFCs) of the ITER machine. Therefore, it is essential to perform an assessment of the behavior of PFCs under cycling heat loads to demonstrate the fitness for purpose of the selected technologies.This article summarizes the features of high heat flux facilities designed and constructed in the Efremov Institute for the performance of high heat flux (HHF) tests under ITER procurements as well as related R&D works.The TSEFEY-M facility was commissioned in 1994. The main purpose of this facility is thermal fatigue testing of mock-ups with various plasma-facing materials (carbon fiber reinforced composite (CFC), tungsten, beryllium, etc.) and with various cooling agents (water or gas).The ITER divertor test facility (IDTF) was created in the framework of ITER project, specifically for the HHF tests of the vertical targets (inner and outer) and domes of the ITER divertor.After commissioning in 2008, the IDTF facility was qualified in 2012-2013 for HHF tests of ITER PFCs. © 2015 Elsevier B.V.


Veresov O.L.,JSC NIIEFA | Grigorenko S.V.,JSC NIIEFA | Zuev Yu.V.,JSC NIIEFA | Kuzhlev A.N.,JSC NIIEFA | And 6 more authors.
24th Russian Particle Accelerator Conference, RuPAC 2014 | Year: 2014

The results of bench tests of an RF-frequency deuteron accelerator (RFQ) with an output energy of 1 MeV and operating frequency of 433 MHz are presented. The paper describes specific features of the RFQ construction and assembly, RF power supply system and test procedures. Parameters of the facility when operating with a beam energy analyzer and Be target are given. © 2014 CC-BY-3.0 and by the respective authors.


Gavrish Y.,JSC NIIEFA
2014 20th International Workshop on Beam Dynamics and Optimization, BDO 2014 | Year: 2014

Development of the particle accelerators and accelerator-based electro-physical structures are among the main directions of the scientific research at the Efremov Institute. A whole range of accelerator devices was developed in the Institute - designed, manufactured and installed in scientific, producing and health organizations are over 300 of different kinds of accelerators - cyclotrons, linacs, direct-action accelerators and neutron generators. © 2014 IEEE.


Kuznetsov V.,JSC NIIEFA | Gorbenko A.,JSC NIIEFA | Davydov V.,JSC NIIEFA | Kokoulin A.,JSC NIIEFA | And 7 more authors.
Fusion Engineering and Design | Year: 2014

The ITER Divertor Test Facility (IDTF) was designed for the high heat flux tests of outer vertical targets, inner vertical targets and domes of the ITER divertor. This facility was created in the Efremov Institute under the Procurement Arrangement 1.7.P2D.RF (high heat flux tests of the plasma facing units of the ITER divertor). The heat flux is generated by an electron-beam system (EBS), 800 kW power and 60 kV maximum accelerating voltage. The component to be tested is mounted on a manipulator in the vacuum chamber capable of testing objects up to 2.5 m long and 1.5 m wide. The pressure in the vacuum chamber is about 3*10-3 Pa. The parameters of the cooling system and the water quality (deionized water) are similar to the cooling conditions of the ITER divertor. The integrated control system regulates all IDTF subsystems and data acquisition from all diagnostic devices, such as pyrometers, IR-cameras, video cameras, flow, pressure and temperature sensors. Started in 2008, the IDTF was commissioned in 2012 with the testing the outer vertical full-scale prototypes and the completion of the PA 1.7.P2D.RF task. This paper details the main characteristics of the IDTF. © 2014 Elsevier B.V.

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