Abstract

Radioisotope thermoelectric generators (RTG) convert the decay energy of a radioisotope ( 238 Pu) into heat then into electricity. RTGs have been used to power space exploration missions. This review paper studies several crucial features of past and present Static RTGs, for instance the advantages of Static RTGs. In addition it reviews Static RTGs limitations such as the shortage in the amount of 238 Pu in (U.S.A). Furthermore it compares the future Dynamic RTGs with Static RTGs. It indicates the future Dynamic RTGs, which include a thermodynamic cycle, use 2-4 times less amount of 238 Pu. In spite of that, their efficiency is almost 4 times greater than past and present RTGs.

Highlights

  • Radioisotope power production is the process of generating electrical energy from the decay energy of a radioisotope through the use of a radioisotope generator

  • The thermal radioisotope power system’s outputs are dependent on the temperature gradient between a heat source that includes the radioactive source and a cold side. In addition their outputs are greater than the non-thermal radioisotope outputs. These systems started with general purpose heat source-radioisotope thermoelectric generators (GPHS-Radioisotope thermoelectric generators (RTG)) the multi-mission radioisotope thermoelectric generators (MM-RTG) and the future generation will include the advanced Stirling radioisotope power generators (ASRG)

  • All types of radioisotope power systems have a number of Radioisotope power generators have been employed for space exploration missions; for instance since 1961 more than 27 missions have been powered using over 45 radioisotope thermoelectric generators [3,4]

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Summary

Introduction

Radioisotope power production is the process of generating electrical energy from the decay energy of a radioisotope through the use of a radioisotope generator. The most commonly used radioisotopes are the alpha and beta emitters because they do not require the significant shielding as required for gamma emitters These generators can be divided into two categories which are thermal and non-thermal radioisotope power systems. The thermal radioisotope power system’s outputs are dependent on the temperature gradient between a heat source that includes the radioactive source and a cold side. In addition their outputs are greater than the non-thermal radioisotope outputs. The most recent space mission is the Mars Science Laboratory Rover, launched in 2011 This rover uses multi-mission radioisotope thermoelectric generators to generate approximate 114W electricity as the surface operations begin and its fuel is 238Pu [6]. The Structure of GPHS-RTG the heat sink, which is comprised of radiator fins for example 6063 aluminum fin in multi-mission radioisotope thermoelectric generators[7]

The Process of Electrical Power Generation in GPHS-RTG
Solutions to Shortage 238Pu
Dynamic Radioisotope Thermoelectric Generators
Advanced Stirling Radioisotope Power Systems
Advantages and limitations of ASRGs
Conclusions

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