Development of fast breeder reactor technology in India

被引：35

作者：

Puthiyavinayagam, P. ^{[1
]}

Selvaraj, P. ^{[1
]}

Balasubramaniyan, V. ^{[1
]}

Raghupathy, S. ^{[1
]}

Velusamy, K. ^{[1
]}

Devan, K. ^{[1
]}

Nashine, B. K. ^{[1
]}

Kumar, G. Padma ^{[1
]}

Kumar, K. V. Suresh ^{[1
]}

Varatharajan, S. ^{[1
]}

Mohanakrishnan, P. ^{[1
,2
]}

Srinivasan, G. ^{[1
,2
]}

Bhaduri, Arun Kumar ^{[1
]}

机构：

[1] Indira Gandhi Ctr Atom Res, Kalpakkam, Tamil Nadu, India

[2] IGCAR, Kalpakkam, Tamil Nadu, India

来源：

PROGRESS IN NUCLEAR ENERGY | 2017年 / 101卷

关键词：

Nuclear energy; Fast reactor; Breeder; Neutronic performance; Fuel cycle; Metal fuel; Technology development; Sodium facilities; Safety studies; Material development; LEAK COLLECTION TRAY; COOLED FAST-REACTOR; PERFORMANCE EVALUATION; STRUCTURAL INTEGRITY; OPERATING EXPERIENCE; HIGH-TEMPERATURE; GAS ENTRAINMENT; STEAM-GENERATOR; HEAT-TRANSFER; SODIUM;

D O I：

10.1016/j.pnucene.2017.03.015

中图分类号：

TL [原子能技术]; O571 [原子核物理学];

学科分类号：

0827 ; 082701 ;

摘要：

India is pursuing a three stage nuclear power program employing its natural uranium and Thorium reserves. FBRs form the second stage of the program linking the first phase with natural U and third phase with Th fuels. The saga of FBR technology development in India is presented in this paper. The valuable experience in design and operation of Fast Breeder Test Reactor (FBTR) is recounted briefly. The R&D for the techno-economic demonstration of Prototype Fast Breeder Reactor (PFBR) is explained including technology development for addressing manufacturing challenges and engineering full-scale qualification. Finally a brief projection is made on the developments for FBR600 with improved safety and economics as well as metal fuel technology for future experimental and power reactors to follow. (C) 2017 Elsevier Ltd. All rights reserved.

引用

页码：19 / 42

页数：24

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