Works matching DE "NUCLEAR reactors management"

Results: 24

The SANS facility at the Pitesti 14MW TRIGA reactor.

Published in:

Crystallography Reports, 2006, v. 51, p. S27, doi. 10.1134/S1063774506070066

By:

Ionita, I.;
Grabcev, B.;
Todireanu, S.;
Constantin, F.;
Shvetsov, V.;
Anghel, E.;
Popescu, G.;
Mincu, M.;
Datcu, A.

Publication type:

Article

JNMM Roundtable.

Published in:: Journal of the Institute of Nuclear Materials Management, 2012, v. 41, n. 1, p. 21
Publication type:: Article

Safeguards-by-Design (SBD) Concepts for Thorium-based Fuel Fabrication Facilities.

Published in:

Journal of the Institute of Nuclear Materials Management, 2012, v. 41, n. 1, p. 43

By:

Gangotra, Suresh;
Grover, R. B.;
Ramakumar, K. L.;
Kamath, H. S.;
Panakkal, J. P.

Publication type:

Article

Great East Japan Earthquake, Tsunami, and Fukushima Daiichi's Accident.

Published in:

2012

By:

Yoshinori Meguro

Publication type:

Speech

Report of the 53rd INMM Annual Meeting.

Published in:

2012

By:

Mladineo, Stephen V.

Publication type:

Proceeding

FEASIBILITY OF REDUCED BORON CONCENTRATION OPERATION IN PRESSURIZED WATER REACTOR PLANTS.

Published in:

Nuclear Technology, 2011, v. 176, n. 1, p. 40, doi. 10.13182/NT176-40

By:

AUNG THARN DAING;
MYUNG-HYUN KIM

Publication type:

Article

EXPERIMENTAL STUDY ON THE BEHAVIOR OF SUSPENDED AEROSOLS OF SODIUM AND NONRADIOACTIVE FISSION PRODUCTS (SrO2 AND CeO2) IN A CLOSED VESSEL.

Published in:

Nuclear Technology, 2011, v. 176, n. 1, p. 83, doi. 10.13182/NT11-A12544

By:

SUBRAMANIAN, V.;
BASKARAN, R.;
MISRA, J.;
INDIRA, R.

Publication type:

Article

ANALYSIS OF THE BR2 LOSS-OF-FLOW TEST A.

Published in:

Nuclear Technology, 2011, v. 176, n. 1, p. 93, doi. 10.13182/NT11-A12545

By:

TZANOS, CONSTANTINE P.;
DIONNE, B.

Publication type:

Article

FLASHING-INDUCED INSTABILITY ANALYSIS AND THE START-UP OF NATURAL CIRCULATION BOILING WATER REACTORS.

Published in:

Nuclear Technology, 2011, v. 176, n. 1, p. 57, doi. 10.13182/NT11-A12542

By:

HU, RUI;
KAZIMI, MUJID S.

Publication type:

Article

Influence of disturbances in the geometry of the elements of a regularly porous system on the hydrodynamic characteristics of the clusters of fuel elements of a nuclear reactor.

Published in:

Journal of Engineering Physics & Thermophysics, 2008, v. 81, n. 2, p. 388, doi. 10.1007/s10891-008-0047-y

By:

D’yakov, E.;
Konyukhov, G.;
Konyukhov, V.

Publication type:

Article

Development of Technological Equipment for RBMK Service-Life Extension.

Published in:

Atomic Energy, 2018, v. 123, n. 5, p. 314, doi. 10.1007/s10512-018-0345-1

By:

Fedosovskii, M. E.;
Dunaev, V. I.;
Gurin, D. A.;
Slobodchikov, A. V.;
Kharakhnin, S. N.

Publication type:

Article

Computational and Experimental Validation of the Serviceability of CPS Actuators Under RBMK Graphite Stack Distortion Conditions.

Published in:

Atomic Energy, 2018, v. 123, n. 5, p. 307, doi. 10.1007/s10512-018-0344-2

By:

Mel’nikov, O. P.;
Kushnarev, P. A.;
Petrov, M. B.;
Lemekhov, Yu. V.

Publication type:

Article

Computational and Experimental Validation of the Serviceability of RBMK Core Elements Under Graphite Stack Distortion Conditions.

Published in:

Atomic Energy, 2018, v. 123, n. 5, p. 302, doi. 10.1007/s10512-018-0343-3

By:

Evropin, S. V.;
Rakhmanov, A. P.;
Churakova, E. V.;
Baranov, I. M.;
Usov, S. M.

Publication type:

Article

Service Life Restoration Technology for RBMK: Design, Implementation, and Assimilation Experience.

Published in:

Atomic Energy, 2018, v. 123, n. 5, p. 293, doi. 10.1007/s10512-018-0342-4

By:

Adamov, E. O.;
Dragunov, Yu. G.;
Slobodchikov, A. V.;
Mikhailov, M. N.;
Petrov, A. A.;
Ukharov, S. G.;
Burlakov, E. V.;
Asmolov, V. G.;
Chernikov, O. G.;
Bystrikov, A. A.;
Kudryavtsev, K. G.;
Lozhnikov, I. N.;
Kharakhnin, S. N.

Publication type:

Article

Environmental and Safety Concerns for Nuclear Power Generation in Ghana.

Published in:: Environmental Research, Engineering & Management / Aplinkos Tyrimai, Inžinerija ir Vadyba, 2011, v. 55, n. 1, p. 49
Publication type:: Article

Sweden could build up to ten nuclear reactors.

Published in:: TCE: The Chemical Engineer, 2016, n. 901/902, p. 17
Publication type:: Article

Entropy Generation Minimization in Dimethyl Ether Synthesis: A Case Study.

Published in:

Journal of Non-Equilibrium Thermodynamics, 2018, v. 43, n. 2, p. 111, doi. 10.1515/jnet-2017-0050

By:

Kingston, Diego;
Razzitte, Adrián César

Publication type:

Article

Students’ assessment of interactive distance experimentation in nuclear reactor physics laboratory education.

Published in:

European Journal of Engineering Education, 2013, v. 38, n. 5, p. 512, doi. 10.1080/03043797.2013.811476

By:

Malkawi, Salaheddin;
Al-Araidah, Omar

Publication type:

Article

Perspective on modeling light water reactor fuel performance.

Published in:

JOM: The Journal of The Minerals, Metals & Materials Society (TMS), 2011, v. 63, n. 8, p. 48, doi. 10.1007/s11837-011-0137-8

By:

Wirth, B. D.;
Stanek, C. R.;
Edsinger, K.

Publication type:

Article

A Methodology for Optimizing the Management of Spent Fuel of Nuclear Power Plants Using Dry Storage Casks.

Published in:

Science & Technology of Nuclear Installations, 2019, p. 1, doi. 10.1155/2019/4309545

By:

Gomes, Ian B.;
Saldanha, Pedro L. Cruz;
Alvim, Antonio Carlos M.

Publication type:

Article

Development and Verification of a Transient Analysis Tool for Reactor System Using Supercritical CO2 Brayton Cycle as Power Conversion System.

Published in:

Science & Technology of Nuclear Installations, 2018, p. 1, doi. 10.1155/2018/6801736

By:

Wu, Pan;
Gao, Chuntian;
Shan, Jianqiang

Publication type:

Article

Modelling of Severe Accident and In-Vessel Melt Retention Possibilities in BWR Type Reactor.

Published in:

Science & Technology of Nuclear Installations, 2018, p. 1, doi. 10.1155/2018/7162387

By:

Valinčius, Mindaugas;
Kaliatka, Tadas;
Kaliatka, Algirdas;
Ušpuras, Eugenijus

Publication type:

Article

ANSWERS computer codes: verification and validation for novel reactor applications.

Published in:

Nuclear Future, 2015, v. 11, n. 3, p. 48

By:

Lillington, John;
Hosking, Glynn;
Smith, Paul;
Smith, Peter

Publication type:

Article

Snaking around a CANDU reactor.

Published in:: Nuclear Future, 2010, v. 6, n. 6, p. 335
Publication type:: Article

Works matching DE "NUCLEAR reactors management"

The SANS facility at the Pitesti 14MW TRIGA reactor.

JNMM Roundtable.

Safeguards-by-Design (SBD) Concepts for Thorium-based Fuel Fabrication Facilities.

Great East Japan Earthquake, Tsunami, and Fukushima Daiichi's Accident.

Report of the 53rd INMM Annual Meeting.

FEASIBILITY OF REDUCED BORON CONCENTRATION OPERATION IN PRESSURIZED WATER REACTOR PLANTS.

EXPERIMENTAL STUDY ON THE BEHAVIOR OF SUSPENDED AEROSOLS OF SODIUM AND NONRADIOACTIVE FISSION PRODUCTS (SrO<sub>2</sub> AND CeO<sub>2</sub>) IN A CLOSED VESSEL.

ANALYSIS OF THE BR2 LOSS-OF-FLOW TEST A.

FLASHING-INDUCED INSTABILITY ANALYSIS AND THE START-UP OF NATURAL CIRCULATION BOILING WATER REACTORS.

Influence of disturbances in the geometry of the elements of a regularly porous system on the hydrodynamic characteristics of the clusters of fuel elements of a nuclear reactor.

Development of Technological Equipment for RBMK Service-Life Extension.

Computational and Experimental Validation of the Serviceability of CPS Actuators Under RBMK Graphite Stack Distortion Conditions.

Computational and Experimental Validation of the Serviceability of RBMK Core Elements Under Graphite Stack Distortion Conditions.

Service Life Restoration Technology for RBMK: Design, Implementation, and Assimilation Experience.

Environmental and Safety Concerns for Nuclear Power Generation in Ghana.

Sweden could build up to ten nuclear reactors.

Entropy Generation Minimization in Dimethyl Ether Synthesis: A Case Study.

Students’ assessment of interactive distance experimentation in nuclear reactor physics laboratory education.

Perspective on modeling light water reactor fuel performance.

A Methodology for Optimizing the Management of Spent Fuel of Nuclear Power Plants Using Dry Storage Casks.

Development and Verification of a Transient Analysis Tool for Reactor System Using Supercritical CO<sub>2</sub> Brayton Cycle as Power Conversion System.

Modelling of Severe Accident and In-Vessel Melt Retention Possibilities in BWR Type Reactor.

ANSWERS computer codes: verification and validation for novel reactor applications.

Snaking around a CANDU reactor.