scholarly journals Summary of the radiological assessment of the fuel cycle for a thorium-uranium carbide-fueled fast breeder reactor

1980 ◽  
Author(s):  
V.J. Tennery ◽  
E.S. Bomar ◽  
W.D. Bond ◽  
H.R. Meyer ◽  
L.E. Morse ◽  
...  
Keyword(s):  
Fuel Cycle ◽  
Fast Breeder Reactor ◽  
Radiological Assessment ◽  
Uranium Carbide

The Potential of Different Concepts of Fast Breeder Reactor for the French Fleet Renewal

2006 ◽  
Author(s):  
Simone Massara ◽  
Philippe Tetart ◽  
David Lecarpentier ◽  
Claude Garzenne ◽  
Alexandre Mourogov
Keyword(s):  
Spent Nuclear Fuel ◽  
Fuel Cycle ◽  
Natural Uranium ◽  
Fast Breeder Reactor ◽  
Simulation Code ◽  
Cycle Simulation ◽  
Waste Production ◽  
Highly Sensitive ◽  
Xxist Century ◽  
Transition Scenario

The performances of different concepts of Fast Breeder Reactor (Na-cooled, He-cooled and Pb-cooled FBR) for the current French fleet renewal are analyzed in the framework of a transition scenario to a 100% FBR fleet at the end of the XXIst century. Firstly, the modeling of these three FBR types by means of a semi-analytical approach in TIRELIRE - STRATEGIE, the EDF fuel cycle simulation code, is presented, together with some validation elements against ERANOS, the French reference code system for neutronic FBR analysis (CEA). Afterwards, performances comparisons are made in terms of maximum deployable power, natural uranium consumption and waste production. The results show that the FBR maximum deployable capacity, independently from the FBR technology, is highly sensitive to the fuel cycle options, like the spent nuclear fuel cooling time or the Minor Actinides management strategy. Thus, some of the key parameters defining the dynamic of FBR deployment are highlighted, to inform the orientation of R&D in the development and optimization of these systems.

Design of 500 MWe Metal Fuel Demonstration Fast Reactor

2014 ◽  
Author(s):  
Chellapandi Perumal ◽  
V. Balasubramaniyan ◽  
P. Puthiyavinayagam ◽  
Raghupathy Sundararajan ◽  
Madhusoodanan Kanakkil ◽  
...  
Keyword(s):  
Nuclear Power ◽  
Large Scale ◽  
Fuel Cycle ◽  
Natural Uranium ◽  
Industrial Scale ◽  
Fast Breeder Reactor ◽  
Spent Fuel ◽  
Metal Fuel ◽  
Water Reactors ◽  
Breeder Reactors

Indian nuclear power programme is being implemented in three stages taking in to consideration limited uranium resources and vast thorium resources in the country. The first stage consists of investing natural uranium in Pressurized Heavy Water Reactors (PHWR). This stage has the potential of 10 GWe. The second stage involves large scale deployment of Fast Breeder Reactors (FBR) with co-located fuel cycle facilities to utilize the plutonium and depleted uranium extracted from the PHWR spent fuel. This stage has a potential of about 300 GWe. In the third stage, effective utilization of the vast thorium resources is planned. Indira Gandhi Centre for Atomic Research (IGCAR) instituted in 1971 at Kalpakkam, is involved in the mission of developing the technology of FBR. A host of multidisciplinary laboratories are established in the centre around the central facility of the 40 MWt Fast Breeder Test Reactor (FBTR). Presently, the construction of indigenously designed MOX fueled 500 MWe Prototype Fast Breeder Reactor (PFBR) that started in 2003 is in advanced stage and commissioning activities are underway. The design of PFBR incorporates several state-of-art features and is foreseen as an industrial scale techno-economic viability demonstrator for the FBR program. Beyond PFBR, the proposal is to build one twin unit having two reactors, with each of improved design compared to PFBR, to be commissioned by 2025. Subsequently, towards rapid realization of nuclear power, the department is planning a series of metal fueled FBRs starting with a 500 MWe Metal fuel Demonstration Fast Breeder Reactor (MDFR-500) to be followed by industrial scale 1000 MWe metal fueled reactors. The paper discusses in detail the above aspects and highlights the activities carried out towards designing MDFR.

Impact of Partitioning and Transmutation on High-Level Waste Disposal for the Fast Breeder Reactor Fuel Cycle

2010 ◽  
Vol 47 (12) ◽  
pp. 1101-1117 ◽  
Author(s):  
Kenji NISHIHARA ◽  
Hiroyuki OIGAWA ◽  
Shinichi NAKAYAMA ◽  
Kiyoshi ONO ◽  
Hiroki SHIOTANI
Keyword(s):  
Waste Disposal ◽  
Fuel Cycle ◽  
Reactor Fuel ◽  
High Level Waste ◽  
Fast Breeder Reactor ◽  
High Level ◽  
Partitioning And Transmutation

Improved analysis on multiple recycling of fuel in prototype fast breeder reactor in a closed fuel cycle

Pramana ◽  
2011 ◽  
Vol 77 (2) ◽  
pp. 315-333 ◽  
Author(s):  
G PANDIKUMAR ◽  
V GOPALAKRISHNAN ◽  
P MOHANAKRISHNAN
Keyword(s):  
Fuel Cycle ◽  
Fast Breeder Reactor ◽  
Closed Fuel Cycle ◽  
Multiple Recycling

A Radiological Assessment of Reprocessing Advanced Liquid-Metal Fast Breeder Reactor Fuels

1978 ◽  
Vol 37 (3) ◽  
pp. 328-339 ◽  
Author(s):  
J. E. Till ◽  
E. S. Bomar ◽  
L. E. Morse ◽  
V. J. Tennery
Keyword(s):  
Liquid Metal ◽  
Fast Breeder Reactor ◽  
Radiological Assessment

Present Status of Fast Breeder Reactor Fuel Cycle Development at PNC

1990 ◽  
Vol 89 (2) ◽  
pp. 194-202
Author(s):  
Masao Yamamoto ◽  
Ken-Ichi Matsumoto
Keyword(s):  
Present Status ◽  
Fuel Cycle ◽  
Reactor Fuel ◽  
Fast Breeder Reactor
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