Study on Enhanced Performance Sodium-Cooled Metal Fuel Core Concepts by Adopting Advanced Fuel and Flexible Design Criteria

Author(s):  
Noboru Kobayashi ◽  
Takashi Ogawa ◽  
Shigeo Ohki ◽  
Tomoyasu Mizuno ◽  
Takanari Ogata

The metal fuel core is superior to the mixed oxide fuel core because of its higher breeding ratio and compact core size resulting from neutron economics, hard neutron spectrum, and high content of heavy metal nuclides. Meanwhile, the metal fuel core exhibits the characteristic of a lower allowable maximum cladding temperature. Utilizing the advantage of the metal fuel core, conceptual sodium-cooled fast breeder reactor designs have been pursued for the attractive core properties of high breeding ratio, small inventory, compact size, low sodium void reactivity, and high transmutation ratio of the minor actinides. Among attractive cores, a conceptual design for a high breeding ratio was performed without blanket fuels. The design conditions were set so a sodium void reactivity of less than 8 $, a core height of less than 150 cm, a maximum cladding temperature of 650 °C, and a fuel pin bundle pressure drop of 0.4MPa. The breeding ratio of the resultant core was 1.34 without blanket fuels.

2021 ◽  
Vol 3 (1) ◽  
pp. 13-18
Author(s):  
Ratna Dewi Syarifah ◽  
Nabil Nabhan MH ◽  
Zein Hanifah ◽  
Iklimatul Karomah ◽  
Ahmad Muzaki Mabruri

Analysis of fuel volume fraction with uranium caride fuel in Gas Cooled Fast Reactor (GFR) with SRAC Code is has been done. The calculation used SRAC Code (Standard Reactor Analysis Code) which is developed by JAEA (Japan Atomic Energy Agency), and the data libraries nuclear used JENDL 4.0. There are two calculation has been used, fuel pin cell calculation (PIJ Calculation) and core calculation (CITATION Calculation). In core calculation, the leakage is calculated so the calculation more precise. The CITATION calculation use two type of core configuration, i.e. homogeneous core configuration and heterogeneous core configuration. The power density value of two type core configuration is quite difference. It is better use heterogeneous core configuration than homogeneous core configuration, because the power density of heterogeneous core configuration is flatter than the other. From the analysis of fuel volume fraction, when the volume fraction is increase, the k-eff value is increase. And the optimum design after has been analysis for fuel volume fraction, that is the fuel volume fraction is 49% with a heterogeneous core configuration of three types of fuel percentages, for Fuel1 9%, Fuel2 12% and Fuel3 15%. This reactor is cylindrical, has a core diameter of 240 cm and a core height of 100 cm.


1994 ◽  
Vol 107 (3) ◽  
pp. 340-355 ◽  
Author(s):  
Gary R. Smolen ◽  
Raymond C. Lloyd ◽  
Tadakuni Matsumoto

1985 ◽  
Vol 22 (2) ◽  
pp. 155-157 ◽  
Author(s):  
Toshimichi TACHIBANA ◽  
Tsuyoshi OHMORI ◽  
Sadamu YAMANOUCHI ◽  
Toshiyuki ITAKI

2009 ◽  
Vol 3 (1) ◽  
pp. 126-135 ◽  
Author(s):  
Noboru KOBAYASHI ◽  
Takashi OGAWA ◽  
Shigeo OHKI ◽  
Tomoyasu MIZUNO ◽  
Takanari OGATA

Author(s):  
Vijayashree Raju ◽  
Rajan Babu Vinayagamoorthy ◽  
Parthasarathy Uppala ◽  
Sureshkumar Ramachandran ◽  
Raghupathy Sundararajan ◽  
...  

Prototype Fast Breeder Reactor (PFBR), India’s first commercial fast breeder reactor employing fast fission is a challenging project from technological point of view to meet the energy security of the country. PFBR is a sodium cooled fast reactor. There are 198 fuel sub assemblies with mixed oxide fuel in the reactor. The fuel is provided with a leak tight metal cladding for containment of the fission products. There are risks of sodium circuit contamination and the fission products blocking the coolant flow to the fuel sub assemblies in case of clad rupture and release of solid fission products into the coolant. Hence PFBR is equipped with an elaborate failed fuel detection and location system. Failed Fuel Location Module is one of the subsystems used to identify the sub-assembly having fuel pins with clad failure. This paper discusses about the conceptual design, design specifications, detailed design, manufacture, assembly and some of the results of functional testing of failed fuel location module of PFBR.


Author(s):  
Chellapandi Perumal ◽  
V. Balasubramaniyan ◽  
P. Puthiyavinayagam ◽  
Raghupathy Sundararajan ◽  
Madhusoodanan Kanakkil ◽  
...  

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.


2011 ◽  
Vol 416 (1-2) ◽  
pp. 151-157 ◽  
Author(s):  
I. Sato ◽  
K. Katsuyama ◽  
Y. Arai

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