P. L. Kirillov

发表

MIF-SKD computation code for thermohydraulic design of a reactor core cooled by supercritical-pressure water

A. P. Sorokin, G. P. Bogoslovskaya, A. A. Karpenko, 2009 .

Changing over to supercritical parameters: The way to advance nuclear power stations with water-cooled reactors

P. L. Kirillov, 2001 .

Addendum and comments to the paper 1995 look-up table for calculating critical heat flux in tubes

P. L. Kirillov, 1997 .

The General Post-CHF Heat Transfer Prediction Method for Tubes on the Base of the Look-up Table

V. N. Vinogradov, V. V. Sergeev, P. L. Kirillov, 1998 .

Development of the system of reactor thermophysical data on the basis of ontological modelling

V. Yu. Zitserman, A. O. Erkimbaev, P. L. Kirillov, 2017 .

Prospects for development of an innovative water-cooled nuclear reactor for supercritical parameters of coolant

G. P. Bogoslovskaya, P. L. Kirillov, S. G. Kalyakin, 2014 .

Simulation of heat transfer processes in the containment shell of a nuclear power station with VVER reactors

V. V. Bezlepkin, P. L. Kirillov, V. V. Smirnov, 1995 .

The fourth international conference on nuclear engineering (ICONE-4)

P. L. Kirillov, P. Kirillov, 1997 .

Critical heat fluxes in triangular rod bundles (the 1997 version of the lookup table)

V. P. Bobkov, P. L. Kirillov, V. N. Vinogradov, 1999 .

Calculation of post-crisis heat transfer in channels

P. L. Kirillov, S. L. Dorokhovich, 2004 .

Supercritical water cooled reactors

P. L. Kirillov, P. Kirillov, 2008 .

Main lines of scientific research in the thermohydraulics of nuclear power installations (part 2)

P. L. Kirillov, 2005 .

Appendix A1 – Additional materials (schematics, layouts, T–s diagrams, basic parameters, and photos) on thermal and nuclear power plants 1

P. L. Kirillov, I. L. Pioro, I. Pioro, 2016 .

The some lines of scientific research in the thermal hydraulics of nuclear power installations (Part I)

P. L. Kirillov, 2005 .

Ontologies and databases on thermophysical properties of nuclear reactor materials

P. L. Kirillov, Vladimir G. Pronyaev, Igor’ Aleksandrovich Chusov, 2019, Nuclear Energy and Technology.

On the look-up tables for the critical heat flux in tubes (history and problems)

P. L. Kirillov, I. P. Smogalev, P. Kirillov, 1995 .

Part 1: Pros and Cons of Commercial Reactor Designs

P. L. Kirillov, R. Pioro, I. Pioro, 2021 .

The 1995 look-up table for critical heat flux in tubes

E. Royer, V. N. Vinogradov, P. L. Kirillov, 1996 .

Heat transfer under supercritical pressures and heat transfer deterioration boundaries

P. L. Kirillov, V. A. Grabezhnaya, P. Kirillov, 2006 .

Current Status of Reactors Deployment and Small Modular Reactors Development in the World

Igor Pioro, P. L. Kirillov, Romney B. Duffey, 2020 .

Heat Transfer in Pipes and Rod Bundles During Flow of Supercritical-Pressure Water

P. L. Kirillov, V. A. Grabezhnaya, 2004 .

A study of heat transfer to molten sodium in tubes

P. L. Kirillov, V. I. Subbotin, P. Kirillov, 1963 .

Heat Transfer in Turbulent Flow. Part 2. Velocity and Temperature Distributions

P. L. Kirillov, P. Kirillov, 2017 .

Supercritical-Pressure Water Nuclear Reactors

P. L. Kirillov, V. M. Poplavskii, V. N. Sharapov, 2004 .

Generalization of experimental data on heat transfer in molten metals

P. L. Kirillov, P. Kirillov, 1963 .

Current Status and Future Developments in Nuclear-Power Industry of the World

P. L. Kirillov, R. Machrafi, R. Pioro, 2019, Journal of Nuclear Engineering and Radiation Science.