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Thomas Godfroy

Bio: Thomas Godfroy is an academic researcher from Marshall Space Flight Center. The author has contributed to research in topics: Stirling engine & Nuclear power. The author has an hindex of 6, co-authored 29 publications receiving 126 citations.

Papers
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Proceedings ArticleDOI
09 Jul 2018
TL;DR: The Kilopower nuclear ground testing (Kilopower Reactor Using Stirling Technology) was completed at the Nevada Nuclear Security Site (NNSS) on March 21, 2018 as discussed by the authors.
Abstract: The Kilopower nuclear ground testing nicknamed KRUSTY (Kilopower Reactor Using Stirling TechnologY) was completed at the Nevada Nuclear Security Site (NNSS) on March 21, 2018. This full scale nuclear demonstration verified the Kilopower reactor neutronics during startup, steady state, and transient operations in a space simulated environment. This was the first space reactor test completed for fission power systems in over 50 years and marked a turning point in NASA's nuclear program. The completed reactor power system design incorporated flight prototypic materials and full scale components in an effort to study the reactor dynamics at full power and significantly reduce follow on risk of a future flight demonstration. This design provided a unique opportunity for the power system to simulate several expected and unexpected mission scenarios that allowed the designers to verify that the reactor dynamics could tolerate many worst case conditions regarding reactor stability and control. The dynamic changes imposed on the reactor validated the ability of the reactor to load follow the power conversion system and passively control the fuel temperature and overall system stability. With successful completion of the KRUSTY experiment, the NASA/DOE team will evaluate the lessons learned throughout the project and apply them towards a flight demonstration of a Kilopower reactor.

48 citations

Journal ArticleDOI
TL;DR: The Kilowatt Reactor Using Stirling Technology (KRUSTY) project as discussed by the authors was the first attempt to demonstrate the nuclear operation of a Kilopower Reactor.
Abstract: The Kilowatt Reactor Using Stirling TechnologY (KRUSTY) was a reactor design, development, and test program to demonstrate the nuclear operation of a Kilopower reactor. Kilopower systems are intend...

45 citations

Journal ArticleDOI
TL;DR: The Kilopower as discussed by the authors was designed to provide a steady-state thermal power range between 4 and 40kW and to convert the heat generated to an electrical output of 1 to 10kW(electric), provid...
Abstract: The Kilopower reactors have been designed to provide a steady-state thermal power range between 4 and 40 kW and to convert the heat generated to an electrical output of 1 to 10 kW(electric), provid...

20 citations

Proceedings ArticleDOI
17 Feb 2004
TL;DR: In this article, the authors describe design features, assembly, and test matrix for the testing of a thermally simulated 32kW direct-drive gas-cooled reactor in the Early Flight Fission Test Facility (EFF‐TF) at Marshall Space Flight Center.
Abstract: One of the power systems under consideration for nuclear electric propulsion is a direct‐drive gas‐cooled reactor coupled to a Brayton cycle. In this system, power is transferred from the reactor to the Brayton system via a circulated closed loop gas. To allow early utilization, system designs must be relatively simple, easy to fabricate, and easy to test using non‐nuclear heaters to closely mimic heat from fission. This combination of attributes will allow pre‐prototypic systems to be designed, fabricated, and tested quickly and affordably. The ability to build and test units is key to the success of a nuclear program, especially if an early flight is desired. The ability to perform very realistic non‐nuclear testing increases the success probability of the system. In addition, the technologies required by a concept will substantially impact the cost, time, and resources required to develop a successful space reactor power system. This paper describes design features, assembly, and test matrix for the testing of a thermally simulated 32kW direct‐drive gas‐cooled reactor in the Early Flight Fission — Test Facility (EFF‐TF) at Marshall Space Flight Center. The reactor design and test matrix are provided by Los Alamos National Laboratories.

13 citations

Proceedings ArticleDOI
17 Jan 2003
TL;DR: The High Power Propulsion Thermal Simulator (HPPTS) as discussed by the authors is designed to enable very realistic non-nuclear testing of space fission systems, which can be used to facilitate research, development, system integration and system utilization via cooperative efforts with DOE labs, industry, universities and other NASA centers.
Abstract: Successful development of space fission systems requires an extensive program of affordable and realistic testing. In addition to tests related to design/development of the fission system, realistic testing of the actual flight unit must also be performed. If the system is designed to operate within established radiation damage and fuel burn up limits while simultaneously being designed to allow close simulation of heat from fission using resistance heaters, high confidence in fission system performance and lifetime can be attained through non-nuclear testing. Through demonstration of systems concepts (designed by DOE National Laboratories) in relevant environments, this philosophy has been demonstrated through hardware testing in the High Power Propulsion Thermal Simulator (HPPTS). The HPPTS is designed to enable very realistic non-nuclear testing of space fission systems. Ongoing research at the HPPTS is geared towards facilitating research, development, system integration, and system utilization via cooperative efforts with DOE labs, industry, universities, and other NASA centers. Through hardware based design and testing, the HPPTS investigates High Power Electric Propulsion (HPEP) component, subsystem, and integrated system design and performance.

13 citations


Cited by
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Journal ArticleDOI
TL;DR: In this paper, the development and technologies of micro heat pipe cooled reactor are overviewed, and difficulties and challenges need to be overcome in the future, including heat pipe cascading failure, fuel enrichment, structure integrity, machining, monolithic thermal stress, inspection and qualification, etc.

88 citations

Journal ArticleDOI
TL;DR: In this paper, a high-temperature waste heat recovery system with heat pipe and thermoelectric generator (TEG) is proposed to resolve the mismatch between energy supply and demand.

56 citations

Journal ArticleDOI
TL;DR: The Kilowatt Reactor Using Stirling Technology (KRUSTY) project as discussed by the authors was the first attempt to demonstrate the nuclear operation of a Kilopower Reactor.
Abstract: The Kilowatt Reactor Using Stirling TechnologY (KRUSTY) was a reactor design, development, and test program to demonstrate the nuclear operation of a Kilopower reactor. Kilopower systems are intend...

45 citations

Journal ArticleDOI
TL;DR: The Kilowatt Reactor Using Stirling TechnologY (KRUSTY) was a prototypic nuclear-powered test of a 5-kW(thermal) Kilopower space reactor as discussed by the authors.
Abstract: The Kilowatt Reactor Using Stirling TechnologY (KRUSTY) was a prototypic nuclear-powered test of a 5-kW(thermal) Kilopower space reactor. This paper presents results from the KRUSTY nuclear system ...

36 citations

Journal ArticleDOI
TL;DR: In this paper, a new conceptual design of a megawatt power level heat pipe cooled space Reactor (HPCR) power system adopted the integrated heatpipe-fuel modules is developed.

28 citations