Burnup calculation of fusion–fission hybrid energy system with thorium cycle

Matsunaka, Masayuki; Shido, S.; Kondo, Keitaro; Miyamaru, Hiroyuki; Murata, Isao

doi:10.1016/j.fusengdes.2007.03.047

Cited by 16 publications

(13 citation statements)

References 2 publications

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“…In the previous study, 13) the FF hybrid system using a thoriumuranium (Th-U) cycle and a uranium-plutonium (U-Pu) cycle fuel was studied by the author's group with the previous burnup calculation system of System 2 and/or System 3 described in Sec. III for two kinds of cooling system of which one was helium gas cooling and the other was liquid water cooling.…”

Section: Analysis Results For Ff Hybrid Reactor 1 Calculation Comentioning

confidence: 99%

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Advanced Burnup Calculation Code System in a Subcritical State with Continuous-Energy Monte Carlo Code for Fusion-Fission Hybrid Reactor

Matsunaka¹,

Ohta²,

Miyamaru³

et al. 2009

Journal of Nuclear Science and Technology

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The fusion-fission (FF) hybrid reactor is a promising energy source that is thought to act as a bridge between the existing fission reactor and the genuine fusion reactor in the future. The burnup calculation system that aims at precise burnup calculations of a subcritical system was developed for the detailed design of the FF hybrid reactor, and the system consists of MCNP, ORIGEN, and postprocess codes. In the present study, the calculation system was substantially modified to improve the calculation accuracy and at the same time the calculation speed as well. The reaction rate estimation can be carried out accurately with the present system that uses track-length (TL) data in the continuous-energy treatment. As for the speed-up of the reaction rate calculation, a new TL data bunching scheme was developed so that only necessary TL data are used as long as the accuracy of the point-wise nuclear data is conserved. With the present system, an example analysis result for our proposed FF hybrid reactor is described, showing that the computation time could really be saved with the same accuracy as before.

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Section: Analysis Results For Ff Hybrid Reactor 1 Calculation Comentioning

confidence: 99%

“…the FF hybrid reactor employing ITER model has been studied aiming at its early realization. 12,13) III. Burnup Calculation System…”

Section: Fusion-fission Hybrid Reactormentioning

confidence: 99%

Advanced Burnup Calculation Code System in a Subcritical State with Continuous-Energy Monte Carlo Code for Fusion-Fission Hybrid Reactor

Matsunaka¹,

Ohta²,

Miyamaru³

et al. 2009

Journal of Nuclear Science and Technology

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“…In many institutes the possibility of using thorium [9][10][11][12][13][14][15][16] in reactors was investigated. Some calculation results of thorium based fuel application in the EPR reactor are presented in the work [16].…”

Section: Preliminary Analysis Of Thorium Based Fuel Application In Thmentioning

confidence: 99%

Analysis of potential advanced thorium based fuel for EPR reactor

Szuta¹

2013

Proceedings of XXI International Baldin Seminar on High Energy Physics Problems — PoS(Baldin ISHEPP XXI)

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As thorium based fuels have benefits in terms of radio-toxicity there are however challenges in terms of reprocessing the spent thorium based fuel. The database and experience of thorium fuels and thorium fuel cycles are very limited , as compared to UO 2 and (U,Pu)O 2 fuels, and need to be augmented before large investments are made for commercial utilization of thorium fuels and fuel cycles.That is why, as the first step of studying the thorium application feasibility, once through thorium based fuel cycle analysis for energy production and radioactive waste transmutation was undertaken, which does not require the technically difficult reprocessing of the spent fuel.The idea is to analyze the thorium based fuel application in the open cycle feasibility study in the existing light water reactors with minimal modifications in order to exploit them.Preliminary analysis of thorium based fuel application in the EPR reactor have shown that once through thorium fuel cycle can be reached with difficulty. It is inferred that the 233 U concentration tends to saturation value which does not depend on power density while the kinetics of reaching the saturation value depends on it.Monte Carlo methodology calculations for the contribution to the analysis of thorium based fuel application in the EPR reactor and in the accelerated driven systems (ADS) were used.

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“…Calculation results for reactor performance of FF hybrid system are described in other paper 6) . Table 1 shows validity confirmation result of the present making procedure of collapsed cross section.…”

Section: Validation Of the Present Collapsing Proceduresmentioning

confidence: 99%

A New Approach to Make Collapsed Cross Section for Burnup Calculation of Subcritical System

Matsunaka

Kondo

Miyamaru

et al. 2008

Journal of Nuclear Science and Technology

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A general-purpose transport and burnup code system for precise analysis of subcritical reactors like a fusionfission (FF) hybrid reactor was developed and used for analyzing their performance. The FF hybrid reactor is a subcritical system, which has a concept of fusion reactor with a blanket region containing nuclear fuel and has been under discussion by author's group for years because the present burnup calculation system mainly consists of a general-purpose Monte Carlo code MCNP-4B, a point burnup code ORIGEN2. JENDL-3.3 pointwise cross section library and JENDL Activation Cross Section File 96 were used as base cross section libraries to make group constant for burnup calculation.A new method has been proposed to make group constant for the burnup calculation as accurate as possible directly using output data of the neutron transport calculation by MCNP and evaluated nuclear data libraries. This method is strict and a general procedure to make one group cross sections in Monte Carlo calculations, while it takes very long computation time. Some speed-up techniques were discussed for the present group constant making process so as to decrease calculation time. Adoption of postprocessing to make group constant improved the calculation accuracy because of increasing number of cross sections to be updated in each burnup cycle.The present calculation system is capable of performing neutronics analysis of subcritical reactors more precise than our previous one. However, at the moment, it still takes long computation time to make group constants. Further speed-up techniques are now under investigation so as to apply the present system to neutronics design analysis for various subcritical systems.

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Burnup calculation of fusion–fission hybrid energy system with thorium cycle

Cited by 16 publications

References 2 publications

Advanced Burnup Calculation Code System in a Subcritical State with Continuous-Energy Monte Carlo Code for Fusion-Fission Hybrid Reactor

Advanced Burnup Calculation Code System in a Subcritical State with Continuous-Energy Monte Carlo Code for Fusion-Fission Hybrid Reactor

Analysis of potential advanced thorium based fuel for EPR reactor

A New Approach to Make Collapsed Cross Section for Burnup Calculation of Subcritical System

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