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Search indexed NASA NTRS and DOE OSTI research on propulsion, heat transfer, battery materials and energy systems. Follow report and document links to the original sources.
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Two dimensional, discrete ordinates transport technique for use with nuclear rocket shielding methods, modification, updating, and data input preparation - Vol. 5
Monte Carlo method, kernel function, and S matrix theory applied to design and analysis radiation shields in nuclear rocket systems
Compilation of neutron and photon cross section data using computer programs developed for nuclear rocket shielding methods, modification, updating, and input data preparation - Vol. 2
Neutron flux and gamma ray source edit computer program for design and analysis of radiation shields in nuclear rocket systems
ODD-K angular flux tape computer program for radiation shielding design and analysis in nuclear rocket systems
Users manual for ODD-K computer program used in radiation shielding design and analysis in nuclear rocket systems
Fortran analytic solution of transport equations by random sampling in radiation shielding design and analysis of nuclear rocket systems
TIC-TOC-TOE computer program for radiation shielding design and analysis in nuclear rocket systems
The approach of matching technology areas with various themes needs was not effective for the materials and thermal control discipline because of the diversity of requirements for each. Top priorities were evolved from the advanced space transportation system and the space power platform because these are essential building blocks in fulfilling some of the other themes. Important needs identified include life long-life cryogenic cooling systems for sensors, masers, and other devices and the needs for lightweight nuclear shielding materials for nuclear electric propulsion.
Monte Carlo method for computing particle and gamma radiation transfer for radiation shielding
Computer program, OPEX 2, determines minimum weight, volume, or cost for shields. Program incorporates improved coding, simplified data input, spherical geometry, and an expanded output. Method is capable of altering dose-thickness relationship when a shield layer has been removed.
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Radiation shielding analysis and development for the Nuclear Cryogenic Propulsion Stage (NCPS) effort is currently in progress and preliminary results have enabled consideration for critical interfaces in the reactor and propulsion stage systems. Early analyses have highlighted a number of engineering constraints, challenges, and possible mitigating solutions. Performance constraints include permissible crew dose rates (shared with expected cosmic ray dose), radiation heating flux into cryogenic propellant, and material radiation damage in critical components. Design strategies in staging can serve to reduce radiation scatter and enhance the effectiveness of inherent shielding within the spacecraft while minimizing the required mass of shielding in the reactor system. Within the reactor system, shield design is further constrained by the need for active cooling with minimal radiation streaming through flow channels. Material selection and thermal design must maximize the reliability of the shield to survive the extreme environment through a long duration mission with multiple engine restarts. A discussion of these challenges and relevant design strategies are provided for the mitigation of radiation in nuclear thermal propulsion.
Measuring fast neutron fluxes in nuclear shielding on background of intense intermediate neutron fluxes
Food for nuclear shielding, thermal protection, structures, containers, fibers, clothing, and ballast
Nuclear reaction cross section data for spacecraft shield design, and for determining radiation dose effect on astronauts
Nuclear cross sections and center of sphere dose calculations for spacecraft radiation shielding research
Bibliography of computer codes on radiation and nuclear shielding