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    Design analysis and risk assessment for a single stage to orbit nuclear thermal rocket

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    Author
    Labib, Satira I.
    Advisor
    King, Jeffrey C.
    Date issued
    2014
    Date submitted
    2014
    Keywords
    NTR
    space exploration
    nuclear thermal rocket
    nuclear propulsion
    nuclear
    Nuclear rockets
    Nuclear rockets -- Risk assessment
    Nuclear rockets -- Design
    Nuclear propulsion
    Propellants
    Nuclear reactors
    
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    URI
    http://hdl.handle.net/11124/12289
    Abstract
    Recent advances in high power density fuel materials have renewed interest in nuclear thermal rockets (NTRs) as a viable propulsion technology for future space exploration. This thesis describes the design of three NTR reactor engines designed for the single stage to orbit launch of payloads from 1-15 metric tons. Thermal hydraulic and rocket engine analyses indicate that the proposed rocket engines are able to reach specific impulses in excess of 700 seconds. Neutronics analyses performed using MCNP5 demonstrate that the hot excess reactivity, shutdown margin, and submersion criticality requirements are satisfied for each NTR reactor. The reactors each consist of a 40 cm diameter core packed with hexagonal tungsten cermet fuel elements. The core is surrounded by radial and axial beryllium reflectors and eight boron carbide control drums. At the same power level, the 40 cm reactor results in the lowest radiation dose rate of the three reactors. Radiation dose rates decrease to background levels ~3.5 km from the launch site. After a one-year decay time, all of the activated materials produced by an NTR launch would be classified as Class A low-level waste. The activation of air produces significant amounts of argon-41 and nitrogen-16 within 100 m of the launch. The derived air concentration, DAC, from the activation products decays to less than unity within two days, with only argon-41 remaining. After 10 minutes of full power operation the 120 cm core corresponding to a 15 MT payload contains 2.5 x 10[superscript 13], 1.4 x 10[superscript 12], 1.5 x 10[superscript 12], and 7.8 x 10[superscript 7] Bq of [superscript 131]I, [superscript 137]Cs, [superscript 90]Sr, and [superscript 239]Pu respectively. The decay heat after shutdown increases with increasing reactor power with a maximum decay heat of 108 kW immediately after shutdown for the 15 MT payload.
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