Prototype fast breeder reactor

Monju is Japan s prototype fast breeder reactor 280 MWe(714MWt), fueled with mixed oxides of plutonium and uranium, cooled tty liquid sodium. Construction was started in 1985 nd initial criticality was attained in April 1994... 

The present status with respect to the fast breeder test reactor operating experience and prototype fast breeder reactor design are presented below. 

Even a change to nuclear energy would help, since the overall cost of the raw material—the uranium ore—would be smaller due to the much smaller quantities required, and the security of supply should be less of a problem since the ore occurs throughout the world, particularly in North America, Southern Africa, Australia and Sweden. The much higher capital costs for the nuclear power station are an important factor which has to be taken into consideration. Prototype fast-breeder reactors have been operated in the U.K. for some years now and when fully developed they could substantially improve the economics of nuclear energy. This is because they enable more energy to be extracted from waste uranium and in addition utilize the plutonium produced in conventional reactors as fuel. 

Prototype Fast Breeder Reactor (PFBR) is a 500 MWe pool type sodium cooled reactor. The 4-loop concept which was taken as the reference for the preliminary design and analysis during 1985-1992 has been reviewed thoroughly mainly from economic considerations. The outcome of these studies helped to arrive at a compact 2-loop concept which is expected to be the fore-runner of commercial FBR in the country. For the 2-loop concept, all the major conceptual issues have been finalised. The main options selected are given below (fig 3)... 

This report describes the development and activities on fast reactor in Japan for the period of April 1996 - March 1997. During this period, the 30th duty cycle operation has been started in the Experimental Fast Reactor "Joyo". The cause investigation on the sodium leak incident has completed and the safety examination are being performed in the Prototype Fast Breeder Reactor "Monju". The three years design study since FY1994 on the plant optimization of the Demonstration FBR has been completed by the Japan Atomic Power Company (JAPC). 

Monju is a prototype fast breeder reactor designed to have an output of 280MWe (714MWt). Monju is fueled with mixed oxides of plutonium and uranium and cooled by liquid sodium. The principal data on plant design and performance are shown in Table 3.1. 

The core of the Japanese prototype fast breeder reactor (PBFR) "Monju" from (Power Reactor and Nuclear Fuel Development Corporation 1980]... 

The prototype fast breeder reactor "Monju was constructed in 1990. The output operation had been carried out and preparations for the full-power operation were being made (O Fig. 58.13). However, it caused sodium leaks from the secondary system on December 8, 1995 and the operation has heen suspended. As of 2009, the overall plant and its functions, including long-stopped as well as improved facilities, have been checked, and preparations to restart operation are under way. 

Prototype fast breeder reactor Monju from (Fuji-ie 2005)... 

To close the fast breeder reactor (FBR) fuel cycle, a fast reactor fuel cycle facility (FRFCF) has long been planned, with construction originally to begin in 2008 and operation to coincide with the need to reprocess the first prototype fast breeder reactor (PFBR) fuel. The PFBR and the next four FBRs to be commissioned by 2020 will use oxide fuel. After that, it is expected that metal fuel with higher breeding capability will be introduced and burn-up is intended to increase from 100 to 200 GWd H. 

PFBR (India) Prototype Fast Breeder Reactor... 

The 500 MW(e) prototype fast breeder reactor (PFBR) is under construction in India. PFBR is a 500 MWe capacity, pool type sodium cooled fast reactor with 2 primary pumps, 4 intermediate heat exchangers and 2 secondary loops. There are 8 integrated steam generator (SG) units 4 per secondary loop where steam at 763 K and 17.2 MPa is produced. Four separate safety grade decay heat exchangers are provided to remove the decay heat directly from the hot pool. The hot and cold pool sodium temperatures are 820 and 670 K, respectively. 

A Prototype Fast Breeder Reactor (PFBR) and Advanced Heavy Water Reactor (AHWR) ... 

The construction of Monju, the prototype fast breeder reactor (FBR) which PNC has built as part of the Japanese FBR development programme, was completed in April 1991, and system start-up tests are presently underway. Monju is a loop-type sodium-cooled fast breeder reactor with U-Pu mixed oxide fuel. It supplies 280 MWe to the grid and is situated on the Tsuruga Peninsula facing the Sea of Japan, about 400 km west of Tokyo. 

Oda, T., et al.. Design and Constraction of Heat Transport Systems of the Prototype Fast Breeder Reactor Monju, Proc. of the Intemat. Conference on Fast Reactors and Related Fuel Cycles, Kyoto, Japan, 1991. 

PROTOTYPE FAST BREEDER REACTOR - DESIGN DESCRIPTION... 

The Prototype Fast Breeder Reactor (PFBR) is a 1250 MWt, 500 MWe pool-type sodium-cooled reactor under design in India. This closely follows the successful construction and commissioning of the experimental reactor FBTR (40 MWt, 13,2 MWe). A brief design description of the various systems is given below. The main characteristics are given in Table... 

Much of the basic technology for the SFR has been established in former fast reactor programs, and was confirmed by the Phenix End-of-Life tests in France by operation of Monju reactor in Japan and the lifetime extension of BN-600 in Russia. New programs involving SFR technology include the China Experimental Fast Reactor, which was connected to the grid in July 2011, India s Prototype Fast Breeder Reactor, and the latest success in Russia with putting into operation the BN-800 reactor. 

CheUapandi, P., Srinivasan, G.S., Chetal, S.C., 2013. Primary containment capacity of prototype fast breeder reactor against core disruptive accident loadings. Nuclear Engineering and Design 256, 178-187. 

Figure 15.15 Prototype fast breeder reactor (PFBR) heat transport systems. SGDHR, Secondary sodium decay heat removal IHX, intermediate heat exchanger.

The prototype fast breeder reactor and its current status... 

Figure 15.16 Design improvements of reactor assembly for FBR-600. dia, diameter ht, height constm, construction SA, suhassemhly PFBR, prototype fast breeder reactor.

Table 15.4 Prototype fast breeder reactor operating parameters...

Figure 15.18 Comparison of 30-m long tube steam generator (SG) of 600-MWe fast breeder reactor (FBR) with the prototype fast breeder reactor (PFBR) SG. OD, outer diameter.

W-SMR (Westinghouse Small Modular Reactor Westinghouse) EM (Energy Multiplier Module General Atomics) PFBR (Prototype Fast Breeder Reactor India)... 

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