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Preliminary report on the promise of accelerator breeding and converter reactor symbiosis (ABACS) as an alternative energy system

Oak Ridge National Lab., TN (USA)

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Abstract

A preliminary study was performed to evaluate the promise of accelerator breeding and converter reactor symbiotic systems (ABACS) as an alternate fission power technology which can make full utilization of the energy content of uranium and thorium ores. ABACS is, therefore, considered as an alternative to fast breeder reactors for extending our energy supply. An explanation is given of the fundamentals of accelerator breeding in which U/sup 233/ or Pu/sup 239/ fissile fuel is produced in a target/blanket system as a result of irradiation with an intense high-energy proton beam. Neutronics and heat transfer analyses are performed for three accelerator breeder concepts based on technologies of the liquid metal fast breeder, molten salt, and gas-cooled fast breeder reactors. Several converter reactors are considered, and the mass flows and economics of the complete symbiosis are presented. Particular attention is given to the potential advantages of ABACS relative to the fast breeder reactor in the areas of inherent safety and in the implementation of the U/sup 233/-U/sup 238/ denatured fuel cycle as a proliferation and diversion deterrent. Advantages and disadvantages of the present accelerator breeder concepts are summarized and development needs are indicated.

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A preliminary study was performed to evaluate the promise of accelerator breeding and converter reactor symbiotic systems (ABACS) as an alternate fission power technology which can make full utilization of the energy content of uranium and thorium ores. ABACS is, therefore, considered as an alternative to fast breeder reactors for extending our energy supply. An explanation is given of the fundamentals of accelerator breeding in which U/sup 233/ or Pu/sup 239/ fissile fuel is produced in a target/blanket system as a result of irradiation with an intense high-energy proton beam. Neutronics and heat transfer analyses are performed for three accelerator breeder concepts based on technologies of the liquid metal fast breeder, molten salt, and gas-cooled fast breeder reactors. Several converter reactors are considered, and the mass flows and economics of the complete symbiosis are presented. Particular attention is given to the potential advantages of ABACS relative to the fast breeder reactor in the areas of inherent safety and in the implementation of the U/sup 233/-U/sup 238/ denatured fuel cycle as a proliferation and diversion deterrent. Advantages and disadvantages of the present accelerator breeder concepts are summarized and development needs are indicated.

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Available abstract

A preliminary study was performed to evaluate the promise of accelerator breeding and converter reactor symbiotic systems (ABACS) as an alternate fission power technology which can make full utilization of the energy content of uranium and thorium ores. ABACS is, therefore, considered as an alternative to fast breeder reactors for extending our energy supply. An explanation is given of the fundamentals of accelerator breeding in which U/sup 233/ or Pu/sup 239/ fissile fuel is produced in a target/blanket system as a result of irradiation with an intense high-energy proton beam. Neutronics and heat transfer analyses are performed for three accelerator breeder concepts based on technologies of the liquid metal fast breeder, molten salt, and gas-cooled fast breeder reactors. Several converter reactors are considered, and the mass flows and economics of the complete symbiosis are presented. Particular attention is given to the potential advantages of ABACS relative to the fast breeder reactor in the areas of inherent safety and in the implementation of the U/sup 233/-U/sup 238/ denatured fuel cycle as a proliferation and diversion deterrent. Advantages and disadvantages of the present accelerator breeder concepts are summarized and development needs are indicated.

Key concepts: Fissile material, Thorium fuel cycle, Natural uranium, Burnup, Nuclear engineering, MOX fuel, Spent nuclear fuel, Uranium-233

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