V. Khripunov

发表

Steady-state operation in compact tokamaks with copper coils

G. G. Gladush, S. Medvedev, V. Lukash, 2011 .

Some technological problems of fusion materials management

M. Zucchetti, B. Kolbasov, K. Tobita, 2014 .

First wall material damage induced by fusion-fission neutron environment

V. Khripunov, 2016 .

Plasma and current drive parameter options for a megawatt range fusion neutron source

V. Lukash, A. Borisov, V. Sergeev, 2009, 2009 23rd IEEE/NPSS Symposium on Fusion Engineering.

Profit from borating concrete in the ITER biological shield

R. T. Santoro, H. Y. Khater, V. Khripunov, 1997, 17th IEEE/NPSS Symposium Fusion Engineering (Cat. No.97CH36131).

Transmutation of plasma facing materials by the neutron flux in a DT fusion reactor

R. Behrisch, V. Khripunov, R. Santoro, 1998 .

Two-dimensional modeling of the fuel assemblies of high-temperature gas-cooled reactors

V. Khripunov, M. Segal’, 1979 .

ITER Nuclear Analysis

C. Varandas, V. Khripunov, R. Santoro, 1997 .

First mirrors in ITER: material choice and deposition prevention/cleaning techniques

V. N. Gorshkov, D. B. Nikitin, V. N. Bondarenko, 2011 .

Issues of a Compact Tokamak Fusion Neutron Source

S. Medvedev, V. Lukash, A. Ivanov, 2010 .

Large-scale collecting mirrors for ITER optical diagnostic

V. Filimonov, A. Dmitriev, V. Khripunov, 2022, Nuclear Fusion.

Radiation and Nuclear Physics Aspects of the Use of the Thorium Fuel Cycle in a Hybrid Fusion Facility

V. Belousov, A. Dudnikov, B. Kuteev, 2022, Fusion Science and Technology.

Intense fusion neutron sources

V. Yu. Sergeev, Boris V. Kuteev, P. R. Goncharov, 2010 .

Absolute measurement of D–T neutron flux with a monitor using activation of flowing water

C. Walker, T. Nishitani, H. Takeuchi, 2001 .

Three-dimensional analysis of nuclear heating in the superconducting magnet system due to gamma-rays from /sup 16/N in the ITER water cooling system of the shielding blanket

V. Khripunov, R. Santoro, R. Plenteda, 1997, 17th IEEE/NPSS Symposium Fusion Engineering (Cat. No.97CH36131).

Progress in International Radioactive Fusion Waste Studies

B. Kolbasov, K. Tobita, R. Testoni, 2019, Fusion Science and Technology.

Estimating Preferences With Random Utility Models.

V. Khripunov, 2012 .

On use of beryllium in fusion reactors: Resources, impurities and necessity of detritiation after irradiation

B. Kolbasov, V. Khripunov, A.Yu. Biryukov, 2016 .

Carbon-14 Source Terms and Generation in Fusion Power Cores

D. K. Kurbatov, V. Khripunov, M. Subbotin, 2008 .

Nuclear performance of the D–D phase of ITER

V. Khripunov, V. Khripunov, 2000 .

Analysis of neutron cameras for ITER

C. Barnes, G. Sadler, M. Sasao, 1999 .

Secondary radiation damage and gas production in plasma facing materials under fusion neutron irradiation

V. Khripunov, 2017 .

Experimental and calculated basis of the lithium capillary system as divertor material

V. Khripunov, A. Vertkov, I. Lyublinski, 1997 .

Heat-pipes-based first wall

V. Khripunov, A. Antipenkov, V. Kovalenko, 1995 .

Radioactive Waste Studies in the Frame of the IEA Cooperative Program on the Environmental, Safety, and Economic Aspects of Fusion Power

Laila A. El-Guebaly, Massimo Zucchetti, B. N. Kolbasov, 2017 .

Nuclear aspects of diagnostics in RTO/RC ITER

C. Walker, A. Costley, L. deKock, 2000 .

Enhanced tritium production in fusion-fission hybrids for the external consumption

B. Kuteev, V. Khripunov, A. Zhirkin, 2019, Fusion Engineering and Design.

ITER radiation shielding and neutronics analysis

M. Sawan, V. Khripunov, R. Santoro, 1998 .

CURRENT VIEW ON THE HYBRID FUSION REACTOR

B. Kuteev, V. Khripunov, 2009 .

SOME THOUGHTS ABOUT BERYLLIUM RESOURCES, IMPURITIES IN IT AND NECESSITY OF ITS DETRITIATION AFTER IRRADIATION

B. Kolbasov, V. Khripunov, A.Yu. Biryukov, 2013 .

Radiation tolerance testing of piezoelectric motors for ITER (first results)

M. Kempenaars, E. Smirnova, G. Kurskiev, 2022, Fusion Engineering and Design.