Plutonium consumption

Moxification of weapons-plutonium diminishes the amount of weapons-grade fissile materials available to potential diversion. A 30 % MOX-loaded reactor has a neutral plutonium output, i.e. plutonium consumption equals plutonium production in the reactor. The difference lies in the quality of the plutonium contained in the fuel after irradiation. 

In 1996, progress was made in the three fields covered by the PAC the demonstration of prototype FBR operation, research into plutonium consumption, and that concerning the destruction of long-lived wastes. 

It is necessary to note, that whereas the first two variants lead to some decrease of weapons grade plutonium consumption rate, the third variant, in addition to effective weapons grade plutonium denaturation, permits burning of minor actinides... 

Switzerland Within the framework of the CAPRA project, the fuel option for amplified plutonium consumption is being studied. In the area of materials for actinide transmutation, the following tasks has been completed in 1994 (1) preparatory experiments and solubility tests for (Ui, PUJ O2 (0.25 < x < 0.65 and for (Uj., PU,J N (0.25 < x< 0.75), as possible materials for the efficient fission of plutonium in a fast neutron flux (2) fabrication of pure PuN-microspheres for ceramic-metal fuel (3) design calculations for sphere-pac segments, based on the idea of a ceramic-metal fiiel (4) material preparation of (U, Zr) N and pelletization tests of TiN and (U, Zr)N for the irradiation experiment in the reactor PHENIX (5) experimental preparations of (Ce,U) O2, (Ce,U,Pu)02 and (Ce, PU)02 for the CAPRA core with lower Pu content, and (6) cleaning of americium from waste streams of the plutonium separation equipment (extraction chromatography). 

The perfecting of a core 3 globally adapted to a total plutonium consumption of about 15 to 20 kg/TWh. Such a performance will be... 

At the time of the core 3 loading, a zone test of several sub-assemblies representing of a core with a very high plutonium consumption. 

The long-awaited demonstrations in Superphenix have a three-fold goal to confirm the capacity of a fast reactor to satisfy the need, to specify the performance of this solution and to provide elements Indispensible for the compatibility of the two processes, plutonium consumption and actinide destruction, carried out simultaneoustly in the same reactor. 

Plutonium consumption and initial plutonium inventory should be as low as possible. 

Mixed oxide fuel becomes insoluble in nitric acid if the plutonium content exceeds about 45%. This places a lower bound on the uranium content, and therefore an upper bound on the net plutonium consumption rate of about 75 kg per TWh of electricity produced, if the fuel is to be oxide and is to be reprocessed by the Purex route. It remains to be determined whether the advantages of higher plutonium consumption, towards the theoretical maximum of about 110 kg per TWh, are sufficient to make alternative fuels, such as nitride, or alternative reprocessing routes attractive. 

The development of a multi-module Gas Turbine - Modular Helium Reactor (GT-MHR) for excess weapons grade plutonium consumption in the Russian Federation in ongoing within an international project that pools together major efforts of the Russian Federation and the USA. The institutions involved in the R D, design and deployment of the plutonium consumption GT-MHR include the following ... 

The GT-MHR for plutonium consumption is at the preliminary design stage. A schedule produced indicates that its prototype could begin full power operation nine years after completion of the preliminary design. This would include the following elements ... 

Funding support for the development of the plutonium consumption version of the GT-MHR is continuing through the DOE NNSA in the United States and Rosatom in the Russian Federation, with additional technology development support from the EU and Japan through ISTC. 

The development and deployment of commercial GT-MHRs is based upon leveraging an ongoing international project to develop and deploy a multi-module GT-MHR designed to consume excess weapons grade plutonium in the Russian Federation, see Section 7.10. The commercial GT-MHR design would utilize the technology development conducted in support of the plutonium consumption version, with the majority of additional development focused on fabrication and qualification of LEU fuel. 

Many of the institutions involved in the R D on the GT-MHR for plutonium consumption would also be involved in transfer of technology from the plutonium consumption version to the commercial GT-MHR. In addition, the GT-MHR Utility Advisory Board (UAB) has been actively supporting the commercialization of the GT-MHR. 

The commercial GT-MHR schedule for a US deployment would parallel the plutonium consumption version schedule summarized in Section 7.10, lagging the deployment in the Russian Federation by about one year. Pre-application licensing interactions with the US Nuclear Regulatory Commission began in 2001, including submittal of a Licensing Plan. 

The GT-MHR reactor design can accommodate alternative fuel cycles if supported by external infrastructure. A fuel cycle utilizing recycled water reactor plutonium can be accommodated, and will be effectively demonstrated by the GT-MHR plutonium consumption project in the Russian Federation. Thorium can be used as an alternative to natural uranium in the fertile particles. If reprocessing is supported in the future, fissile particles can incorporate recycled U from thorium fertile particles to reduce the separative work required to produce fissile particles. 

The ongoing joint United States/Russian Federation project to develop and construct a version of the GT-MHR to consume surplus weapons plutonium is an important element of commercial GT-MHR development. The major systems, structures and components of the GT-MHR, including the power conversion system, reactor vessel and internals, and reactor building, can be developed and demonstrated through this project. The primary alterations to the plutonium consumption design are expected to be in the reactor core and possibly the reactor cavity cooling system, with the remainder of the commercial GT-MHR drawing directly from the plutonium consumption version. 

With the exception of fabrication and qualification of low enriched fuel for the commercial GT-MHR, the technology development and demonstration would be conducted in conjunction with the development and deployment of the plutonium consumption version. Construction of a fuel fabrication pilot plant, and fabrication and irradiation of proof test fuel is estimated to take eight years and could be conducted in parallel with the plant schedule. 

Pu- are considered. Fuel is removed and processed at a rate required to maintain a specified poison level. The reactor consists of a core region in which plutonium is burned and of a blanket region containing uranium and plutonium. Under equilibrium conditions the net rate of production of plutonium in the blanket is eipial to the plutonium consumption in the core, in Table 2-11 are given [2D] some of the nuclear characteristics for... 

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