東華大學圖書館 |

Language: English

Help

回圖書館首頁

手機版館藏查詢

Back

Switch To: Labeled | MARC Mode | ISBD

Development of Thermodynamic Cycles ...

Dragunov, Alexey.

Linked to FindBook

Google Book

Amazon

博客來

Development of Thermodynamic Cycles for Sodium-Cooled-Fast Reactors.

Record Type:	Language materials, printed : Monograph/item
Title/Author:	Development of Thermodynamic Cycles for Sodium-Cooled-Fast Reactors./
Author:	Dragunov, Alexey.
Description:	151 p.
Notes:	Source: Masters Abstracts International, Volume: 52-04.
Contained By:	Masters Abstracts International52-04(E).
Subject:	Engineering, Nuclear. -
Online resource:	http://pqdd.sinica.edu.tw/twdaoapp/servlet/advanced?query=MR96209
ISBN:	9780494962091

Development of Thermodynamic Cycles for Sodium-Cooled-Fast Reactors.
Dragunov, Alexey.

Development of Thermodynamic Cycles for Sodium-Cooled-Fast Reactors. - 151 p.

Source: Masters Abstracts International, Volume: 52-04.

Thesis (M.A.Sc.)--University of Ontario Institute of Technology (Canada), 2014.

Currently, one engineering challenge is designing Generation IV (GEN-IV) Nuclear Power Plants (NPPs) with significantly higher thermal efficiencies compared to current NPPs, and to match, or at least to be close to, the thermal efficiencies reached by fossil-fired power plants, which are currently at the level of 40-62%.

ISBN: 9780494962091Subjects--Topical Terms:

1043651
Engineering, Nuclear.

Development of Thermodynamic Cycles for Sodium-Cooled-Fast Reactors.
LDR:03193nam a2200301 4500 001 1967126
005 20141112075806.5
008 150210s2014 ||||||||||||||||| ||eng d
020 $a 9780494962091
035 $a (MiAaPQ)AAIMR96209
035 $a AAIMR96209
040 $a MiAaPQ $c MiAaPQ
100 1 $a Dragunov, Alexey. $3 2104063
245 1 0 $a Development of Thermodynamic Cycles for Sodium-Cooled-Fast Reactors.
300 $a 151 p.
500 $a Source: Masters Abstracts International, Volume: 52-04.
500 $a Adviser: Igor Pioro.
502 $a Thesis (M.A.Sc.)--University of Ontario Institute of Technology (Canada), 2014.
520 $a Currently, one engineering challenge is designing Generation IV (GEN-IV) Nuclear Power Plants (NPPs) with significantly higher thermal efficiencies compared to current NPPs, and to match, or at least to be close to, the thermal efficiencies reached by fossil-fired power plants, which are currently at the level of 40-62%.
520 $a As there are six GEN-IV nuclear-reactor concepts and the performance of these reactors-concepts depends on their design, it is reasonable to start with all GEN-IV reactor concepts and investigate the coolants and their characteristics in these concepts. For this objective, main thermophysical, corrosion, and neutronic properties of coolants of the GEN-IV reactors within the proposed temperature range of operation were investigated. Heat Transfer Coefficients (HTCs) for the coolants of the GEN-IV concepts were also calculated and compared to typical HTCs published in the open literature for coolant candidates.
520 $a Based on a comparison of properties and HTCs, a Sodium-cooled Fast Reactor (SFR) - one of the six concepts considered under the Generation IV International Forum (GIF), was selected because it is the most experienced reactor technology among all of the proposed GEN-IV reactor concepts. Moreover, with depleting uranium resources, there is an interest to design reactors that operate on a closed fuel cycle, and SFR is one of the potential options. A BN-600 reactor is a sodium-cooled fast-breeder reactor built at the Beloyarsk NPP in Russia, and it is in operation since 1980. On the secondary side it utilizes a subcritical-pressure Rankine-steam cycle with heat regeneration. The power-conversion system is presented, and calculations of thermal efficiency of this scheme have been performed and analyzed.
520 $a To achieve higher thermal efficiency of the plant, one of the possibilities is to increase thermal efficiency of the turbine cycle. Two main approaches for the SFR in terms of the power-conversion cycle were investigated: supercritical-pressure Rankine-"steam" cycle and supercritical-pressure CO2 Brayton-gas-turbine cycle. The feasibility of these options is discussed. The thermal efficiencies of ideal and non-ideal CO2 Brayton gas-turbine cycles were optimized by varying CO2 pressures and temperatures at the outlet of Na-CO2 heat exchanger.
590 $a School code: 1555.
650 4 $a Engineering, Nuclear. $3 1043651
690 $a 0552
710 2 $a University of Ontario Institute of Technology (Canada). $b Energy Systems and Nuclear Engineering. $3 2104064
773 0 $t Masters Abstracts International $g 52-04(E).
790 $a 1555
791 $a M.A.Sc.
792 $a 2014
793 $a English
856 4 0 $u http://pqdd.sinica.edu.tw/twdaoapp/servlet/advanced?query=MR96209