Network


Latest external collaboration on country level. Dive into details by clicking on the dots.

Hotspot


Dive into the research topics where Omar Mireles is active.

Publication


Featured researches published by Omar Mireles.


SPACE TECH.& APPLIC.INT.FORUM-STAIF 2006: 10th Conf Thermophys Applic Microgravity; 23rd Symp Space Nucl Pwr & Propulsion; 4th Conf Human/Robotic Tech & Nat'l Vision for Space Explor.; 4th Symp Space Coloniz.; 3rd Symp on New Frontiers & Future Concepts | 2006

Integration and Utilization of Nuclear Systems on the Moon and Mars

Michael G. Houts; George R. Schmidt; Shannon M. Bragg‐Sitton; Robert Hickman; Andy Hissam; Vance Houston; James Martin; Omar Mireles; David Poston; Bob Reid; Todd A. Schneider; Eric Stewart; Jason Turpin; Melissa Van Dyke; Jason A. Vaughn; David Wagner

Over the past five decades numerous studies have identified nuclear energy as an enhancing or enabling technology for planetary surface exploration missions. This includes both radioisotope and fission sources for providing both heat and electricity. Nuclear energy sources were used to provide electricity on Apollo missions 12, 14, 15, 16, and 17, and on the Mars Viking landers. Very small nuclear energy sources were used to provide heat on the Mars Pathfinder, Spirit, and Opportunity rovers. Research has been performed at NASA MSFC to help assess potential issues associated with surface nuclear energy sources, and to generate data that could be useful to a future program. Research areas include System Integration, use of Regolith as Radiation Shielding, Waste Heat Rejection, Surface Environmental Effects on the Integrated System, Thermal Simulators, Surface System Integration / Interface / Interaction Testing, End‐to‐End Breadboard Development, Advanced Materials Development, Surface Energy Source Coolants, and Planetary Surface System Thermal Management and Control. This paper provides a status update on several of these research areas.


48th AIAA/ASME/SAE/ASEE Joint Propulsion Conference & Exhibit | 2012

Fabrication and Testing of CERMET Fuel Materials for Nuclear Thermal Propulsion

Robert Hickman; Jeramie Broadway; Omar Mireles

A first generation Nuclear Cryogenic Propulsion Stage (NCPS) based on Nuclear Thermal Propulsion (NTP) is currently being developed for Advanced Space Exploration Systems. The overall goal of the project is to address critical NTP technology challenges and programmatic issues to establish confidence in the affordability and viability of NTP systems. The current technology roadmap for NTP identifies the development of a robust fuel form as a critical near term need. The lack of a qualified nuclear fuel is a significant technical risk that will require a considerable fraction of program resources to mitigate. Due to these risks and the cost for qualification, the development and selection of a primary fuel must begin prior to Authority to Proceed (ATP) for a specific mission. The fuel development is a progressive approach to incrementally reduce risk, converge the fuel materials, and mature the design and fabrication process of the fuel element. A key objective of the current project is to advance the maturity of CERMET fuels. The work includes fuel processing development and characterization, fuel specimen hot hydrogen screening, and prototypic fuel element testing. Early fuel materials development is critical to help validate requirements and fuel performance. The purpose of this paper is to provide an overview and status of the work at Marshall Space Flight Center (MSFC).


SPACE TECHNOLOGY AND APPLICATIONS INT.FORUM-STAIF 2005: Conf.Thermophys in#N#Micrograv;Conf Comm/Civil Next Gen.Space Transp; 22nd Symp Space Nucl.Powr#N#Propuls.;Conf.Human/Robotic Techn.Nat'l Vision Space Expl.; 3rd Symp Space Colon.; 2nd#N#Symp.New Frontiers | 2005

Multiple Restart Testing of a Stainless Steel Sodium Heat Pipe Module

James Martin; Omar Mireles; Robert S. Reid

A heat pipe cooled reactor is one of several candidate reactor concepts being considered for space power and propulsion systems to support future space exploration activities. Long life heat pipe modules, with concepts verified through a combination of theoretical analysis and experimental evaluations, would be necessary to establish the viability of this option. A number of stainless steel/sodium heat pipe modules have been designed and fabricated to support experimental testing of a Safe Affordable Fission Engine (SAFE) project, a 100‐kWt core design pursued jointly by the Marshall Space Flight Center and the Los Alamos National Laboratory. One of the SAFE heat pipe modules was successfully subjected to over 200 restarts, examining the behavior of multiple passive freeze/thaw operations. Typical operation included a 1‐hour startup to an average evaporator temperature of 1000 K followed by a 15‐minute hold at temperature. Nominal maximum input power to the evaporator (measured at the power supply) during...


9th Annual International Energy Conversion Engineering Conference | 2011

Design of a Mechanical NaK Pump for Fission Space Power Systems

Omar Mireles; David E. Bradley; Thomas Godfroy

Alkali liquid metal cooled fission reactor concepts are under development for spaceflight power requirements. One such concept utilizes a sodium-potassium eutectic (NaK) as the primary loop working fluid, which has specific pumping requirements. Traditionally, electromagnetic linear induction pumps have been used to provide the required flow and pressure head conditions for NaK systems but they can be limited in performance, efficiency, and number of available vendors. The objective of the project was to develop a mechanical NaK centrifugal pump that takes advantages of technology advances not available in previous liquid metal mechanical pump designs. This paper details the design, engineering prototype build, and anticipated performance test matrix of a mechanical NaK pump developed at NASA Marshall Space Flight Center. The pump was designed to meet reactor cooling requirements using commercially available components modified for high temperature NaK service.


Archive | 2012

Nuclear Cryogenic Propulsion Stage Fuel Design and Fabrication

Robert Hickman; Jeramie Broadway; Omar Mireles; Jon Webb; Lou Qualls


Archive | 2011

Transient Response to Rapid Cooling of a Stainless Steel Sodium Heat Pipe

Omar Mireles; Michael G. Houts


Archive | 2005

Development, Integration and Utilization of Surface Nuclear Energy Sources for Exploration Missions

Michael G. Houts; George R. Schmidt; Shannon Bragg-Sitton; Robert Hickman; Andy Hissam; Vance Houston; James Martin; Omar Mireles; Bob Reid; Todd A. Schneider


Archive | 2015

Optimization of a Wcl6 CVD System to Coat UO2 Powder with Tungsten

Grace A. Belancik; Marvin W. Barnes; Omar Mireles; Robert Hickman


Archive | 2014

Affordable Development and Optimization of CERMET Fuels for NTP Ground Testing

Robert Hickman; Jeramie Broadway; Omar Mireles


Archive | 2013

Status on the Development of CERMET Fuels For A Nuclear Cryogenic Propulsion Stage (NCPS)

Jeramie Broadway; Robert Hickman; Omar Mireles

Collaboration


Dive into the Omar Mireles's collaboration.

Top Co-Authors

Avatar

Robert Hickman

Marshall Space Flight Center

View shared research outputs
Top Co-Authors

Avatar

James Martin

Marshall Space Flight Center

View shared research outputs
Top Co-Authors

Avatar

Michael G. Houts

Marshall Space Flight Center

View shared research outputs
Top Co-Authors

Avatar

Andy Hissam

Marshall Space Flight Center

View shared research outputs
Top Co-Authors

Avatar

Bob Reid

Marshall Space Flight Center

View shared research outputs
Top Co-Authors

Avatar

George R. Schmidt

Marshall Space Flight Center

View shared research outputs
Top Co-Authors

Avatar

Thomas Godfroy

Marshall Space Flight Center

View shared research outputs
Top Co-Authors

Avatar

Todd A. Schneider

Marshall Space Flight Center

View shared research outputs
Top Co-Authors

Avatar

Vance Houston

Marshall Space Flight Center

View shared research outputs
Top Co-Authors

Avatar

David Poston

Marshall Space Flight Center

View shared research outputs
Researchain Logo
Decentralizing Knowledge