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ESA Document - Emits - ESA

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s<br />

HMM<br />

Assessment Study<br />

Report: CDF-20(A)<br />

February 2004<br />

page 404 of 422<br />

Furthermore, the total mass of the systems is one of the key parameters for space reactors, while<br />

virtually non-existent for designing classical terrestrial systems (except submarine reactors). To a<br />

smaller extent this also holds true for its shape and size.<br />

As a result of the above mentioned parameters, space reactor designs show higher reactor core<br />

temperatures and operate with much higher enriched 235 U fuel. This leads to lower core<br />

dimensions and mass, reduced radiator size and mass and higher efficiencies of the conversion<br />

system. In numbers, the enrichment increases from natural-20% for terrestrial up to 93% for<br />

space systems, and the core temperature increases from 400-573 K up to 900-1000 K.<br />

Technically these changes imply the abandon of the pressurised water reactor design for either<br />

liquid metal cooled or gas cooled cores. They furthermore demand the use of materials capable<br />

of withstanding for long times high temperatures as well as high radiation (neutron) fluxes.<br />

6.2.3 Approach<br />

Given the high complexity of designing space nuclear reactors and especially the highly<br />

interrelated subsystem dependencies, it was chosen to not develop a parametrical reactor model<br />

with completely open input parameters but to base the assessment on two recently proposed<br />

space reactor models.<br />

For the present study, the two designs that are taken as reference were recently proposed by<br />

European nuclear industry within an <strong>ESA</strong> contract especially for Martian surface power<br />

generation purposes. They are both available to a technical design level sufficient for the present<br />

study and correspond to the power level as well as lifetime requirements.<br />

6.3 Reactor power subsystems<br />

Some aspects of different reactor power system components are provided. The purpose of this<br />

small section is to provide some basic elements to understand the choices and implications of the<br />

reactor designs proposed.<br />

Reactor core<br />

• Thermal n core: larger (if small: limited core life due to burn-up), moderator, good<br />

negative power coefficient (safety), rather for larger than10 MWe reactors<br />

• Fast n core: enriched fuel, smaller, more stable power distr., low burn-up, small negative<br />

power coefficient (safety), favourable in 100 kWe range<br />

Conversion system<br />

Static<br />

Thermoelectric: mature, space proven; about 4% (adv.: cascades about7%)<br />

Thermionic: mature, in core vs. out core systems, life-time limiting factors,<br />

space reactor proven<br />

AMTEC: immature, different for ionic and electronic condition, short<br />

lifetimes, corrosion problems, 19-25%

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