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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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At least 19 records
All sourcesNASA NTRSDOE OSTI
NASA NTRS1995

Computational Simulation Of A Nuclear Engine

Nuclear Engine System Simulation (NESS) computer program developed to satisfy need for accurate, stand-alone software tool for preliminary design analysis of nuclear thermal propulsion (NTP) engine system. Used for rapid, preliminary detailed design analysis of both reactor and key engine systems. Principal outputs include operating characteristics and weights of reactors, engine-system parameters as performances, weights, dimensions, pressures, temperatures, and mass flows, and operating characteristics of turbopumps under both design and off-design operating conditions. Written in FORTRAN 77.

Walton, J. T.↗
DOE OSTI2020

A Probabilistic Model-Based Diagnostic Framework for Nuclear Engineering Systems

A fault diagnostic framework was investigated in this study for applications in thermal–hydraulic systems of nuclear power plants. The proposed framework consists of quantitative model-based diagnosis, statistical change detection and probabilistic reasoning. The use of physics-based diagnostic models provides high detection sensitivity and allows noise and measurement uncertainty to be incorporated robustly. Performance-related parametric models for each component are constructed based on first principles. Numerical model residuals are generated using the concept of analytical redundancy. Statistical change detection methods are employed to detect non-zero residuals in the presence of uncertainty. The diagnosis task is performed using Bayesian inference to detect and localize possible faults. Application to a single-phase heat exchanger for demonstration showed that the proposed probabilistic framework can provide improved results in comparison with traditional approaches while remaining less sensitive to false alarms in the presence of measurement and modeling uncertainty.

Bayesian network↗
NASA NTRS2008

Evaluation of Recent Upgrades to the NESS (Nuclear Engine System Simulation) Code

The Nuclear Thermal Rocket (NTR) concept is being evaluated as a potential propulsion technology for exploratory expeditions to the moon, Mars, and beyond. The need for exceptional propulsion system performance in these missions has been documented in numerous studies, and was the primary focus of a considerable effort undertaken during the Rover/NERVA program from 1955 to 1973. The NASA Glenn Research Center is leveraging this past NTR investment in their vehicle concepts and mission analysis studies with the aid of the Nuclear Engine System Simulation (NESS) code. This paper presents the additional capabilities and upgrades made to this code in order to perform higher fidelity NTR propulsion system analysis and design, and a comparison of its results to the Small Nuclear Rocket Engine (SNRE) design.

Fittje, James E.↗
DOE OSTI2016

Brief 76 Nuclear Engineering Enrollments and Degrees Survey, 2015 Data

The 2015 Nuclear Engineering Enrollments and Degrees Survey reports degrees granted between September 1, 2014 and August 31, 2015. Enrollment information refers to the fall term 2015. The enrollments and degrees data comprises students majoring in nuclear engineering or in an option program equivalent to a major. Thirty-five academic programs reported having nuclear engineering programs during 2015, and data was received from all thirty-five programs. The report includes enrollment information on undergraduate students and graduate students and information by degree level for post-graduation plans.

99 GENERAL AND MISCELLANEOUS↗
DOE OSTI2016

Enhancement of Nuclear Engineering Technology Degree with a Web-Based PWR Simulator

Reactor plant simulators are used in the nuclear industry for initial and continuous training of reactor operators and senior reactor operators. The use of the generic pressurized water reactor (GPWR) plant simulator is valuable for the nuclear industry as it will ensure graduates of the Bachelor of Science in Nuclear Engineering Technology (BSNET) program will be better trained employees for the nuclear industry and address forecasted workforce shortages in the nuclear industry. By adopting simulation for education, a proven teaching and training method applied extensively in the plant environment, work quality among entrants to the nuclear power workforce will be improved, elevating performance in the field. This includes a positive influence on safety which is paramount to retaining public support of this clean energy source. Much of the research on the use of simulations within courses has argued that simulations are good tools to help students learn key concepts, terminology, and theories within courses. The GPWR simulator provides an opportunity for nuclear engineering technology students to improve their understanding of theoretical concepts associated with nuclear power plants. This hands-on experience will ensure graduates of the BSNET program will be better trained employees for the nuclear industry and address forecasted workforce shortages in the nuclear industry by providing a real-world experience in plant operations. The GPWR simulator will be utilized in five nuclear courses to begin, while providing opportunities for future expansion of the curriculum. All students graduating with a BSNET degree will interact with the simulator, experience better preparing them for further simulator training provided throughout the industry for licensure of operators. (authors)

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS↗
DOE OSTI2022

Historical review and proof-of-concept future method demonstration of adaptive mesh refinement in nuclear engineering for increased fidelity and computational efficiency

As the nuclear industry's use of computational tool increases, the need for increased fidelity and computational efficiency is well known. While most approaches to increased fidelity rely on applying a fine mesh over the problem domain, a more efficient method is to apply an adaptive mesh refinement (AMR) algorithm to the mesh definition. In the field of nuclear engineering, AMR has previously been used in conjunction with deterministic methods, including: S{sub N} transport methods, Lattice Boltzmann Methods, and COMSOL. The future of AMR in nuclear engineering is to couple it to a Monte Carlo code with the goal of reducing calculation time. A proof-of-concept example yielded positive results for using the gradient of the flux as a refinement criteria. The refinement criteria was varied from 0.01 to 0.10, which yielded a recommended range of 0.01 to 0.04, and the number of refinement iterations was varied from 0 to 7, with diminishing returns seen after 5 iterations. After the success of the proof-of-concept exercise, work began on creating a full program coupling MCNP6.2 and the AMR algorithm in the deal.II library. (authors)

22 GENERAL STUDIES OF NUCLEAR REACTORS↗
DOE OSTI2023

Nuclear history, politics, and futures from (A)toms-to(Z)oom: Design and deployment of a remote-learning special-topics course for nuclear engineering education

To address the lack of familiarity with nuclear history common among nuclear engineers and physicists, we outline the design and deployment of a special-topics course entitled “NE290: Nuclear History, Politics, and Futures” throughout which we contextualize the importance of the field at its inception, in current affairs, and in future endeavors. We argue that understanding this history is paramount in internalizing a sense of respect for the scientific, technical, and sociological ramifications of an unlocked atom—as well as its perils. We begin by outlining the gaps in secondary educational offerings for nuclear history and their importance in consideration with nontechnical engineering guidelines. We then outline a number of ABET specifications as pedagogical goals for NE290 from which we derive a list of target student learning objectives. Next, we outline the NE290 syllabus in terms of assignments and an overview of course content in the form of a class timeline. We provide an extensive description of the materials and teaching methodologies for the four units of NE290: Twentieth-Century Physics, Physics in WWII, the Early Cold War, and the Late Cold War and Modern Era. We detail the sequence of lectures across the course and historical timelines leading up to a showcasing of NE290 final projects which mirror in creativity the novelty of course offering. Because NE290 was first offered during Spring 2021 during the COVID-19 pandemic, additional measures in the form of new tools were used to augment the mandate of remote learning. In particular, we leveraged the newfound ubiquity of videoconferencing technology to recruit geographically diverse guest lecturers and used the MIRO tool for virtual whiteboarding. Lastly, we provide an accounting of course outcomes drawn from student feedback which—in tandem with the complete distribution of course material—facilitates the integration of nuclear history into the curriculum for the wider nuclear engineering and physics communities.

Berliner, Aaron J.↗
DOE OSTI2019

Brief 80 Nuclear Engineering Enrollments and Degrees Survey, 2017-2018 Data

The 2018 survey includes degrees granted for the academic years September 2016 – August 2017 and September 2017 – August 2018, and enrollments for fall 2018. Thirty-five nuclear engineering academic programs were surveyed with all 35 responding and data reported from 34 programs. The enrollments and degrees data include students majoring in nuclear engineering or in an option program equivalent to a major. Some nuclear engineering programs have indicated that health physics option enrollments and degrees are also reported in the health physics survey.

99 GENERAL AND MISCELLANEOUS↗
DOE OSTI2014

Brief 72 Nuclear Engineering Enrollments and Degrees Survey, 2013 Data (2-14)

The survey includes degrees granted between September 1, 2012 and August 31, 2013. Enrollment information refers to the fall term 2013. The enrollments and degrees data include students majoring in nuclear engineering or in an option program equivalent to a major. Thirty-two academic programs reported having nuclear engineering programs during 2013, and data was received from all thirty-two programs. The data for two nuclear engineering programs include enrollments and degrees in health physics options that are also reported in the health physics enrollments and degrees data.

99 GENERAL AND MISCELLANEOUS↗
DOE OSTI2015

Brief 74 Nuclear Engineering Enrollments and Degrees Survey, 2014 Data

The 2014 survey includes degrees granted between September 1, 2013 and August 31, 2014, and enrollments for fall 2014. There are three academic programs new to this year's survey. Thirty-five academic programs reported having nuclear engineering programs during 2014, and data were provided by all thirty-five. The enrollments and degrees data include students majoring in nuclear engineering or in an option program equivalent to a major. Two nuclear engineering programs have indicated that health physics option enrollments and degrees are also reported in the health physics enrollments and degrees survey.

99 GENERAL AND MISCELLANEOUS↗
DOE OSTI2018

Safeguards by Design in Nuclear Engineering Design Courses: Engaging Universities in Safeguards by Design

Engaging professionals across the breadth of the nuclear industry to educate them on international safeguards objectives and methodology is logistically challenging, especially in the United States, where individuals may not interact with the IAEA and are not as familiar with implementing international safeguards. However, incorporating international safeguards concepts into the mandatory curriculum of nuclear-related university degree programs around the world, complementary to nuclear safety and security concepts, could reach individuals who will go on to be professionals acting in a variety of roles across the nuclear industry (e.g., developing nuclear-related advanced technologies, designing or operating nuclear facilities, serving as State regulators). This would ultimately lead to more effective and efficient safeguards, including helping to move safeguards by design from a concept to a standard practice, as future designers, operators, and State regulators would be more familiar with international safeguards. This could also potentially address human resource challenges by creating a broader base of individuals knowledgeable about the IAEA mission from which to draw future inspectors and analysts. In order to implement this idea, the Y-12 National Security Complex in Oak Ridge, Tennessee, in conjunction with the Center for Nuclear Security Science & Policy Initiatives (a research institute associated with Texas A&M University), targeted nuclear engineering undergraduate students taking the mandatory design course at Texas A&M and the University of Tennessee. The project objective was to introduce safeguards by design concepts to individuals who are planning to work in a broad range of nuclear-related careers. The paper describes the project methodology, which included the project leads creating and presenting lectures on safeguards to the design class and mentoring teams working on design team projects that incorporated safeguards. The paper also identifies lessons learned while incorporating safeguards topics into nuclear engineering university degree programs.

99 GENERAL AND MISCELLANEOUS↗
NASA NTRS1993

NTP system simulation and detailed nuclear engine modeling

The topics are presented in viewgraph form and include the following: nuclear thermal propulsion (NTP) & detailed nuclear engine modeling; modeling and engineering simulation of nuclear thermal rocket systems; nuclear thermal rocket simulation system; INSPI-NTVR core axial flow profiles; INSPI-NTRV core axial flow profiles; specific impulse vs. chamber pressure; turbine pressure ratio vs. chamber pressure; NERVA core axial flow profiles; P&W XNR2000 core axial flow profiles; pump pressure rise vs. chamber pressure; streamline of jet-induced flow in cylindrical chamber; flow pattern of a jet-induced flow in a chamber; and radiative heat transfer models.

Anghaie, Samim↗
NASA NTRS1988

Summary of aerospace and nuclear engineering activities

The Texas A&M Nuclear and Aerospace engineering departments have worked on five different projects for the NASA/USRA Advanced Design Program during the 1987/88 year. The aerospace department worked on two types of lunar tunnelers that would create habitable space. The first design used a heated cone to melt the lunar regolith, and the second used a conventional drill to bore its way through the crust. Both used a dump truck to get rid of waste heat from the reactor as well as excess regolith from the tunneling operation. The nuclear engineering department worked on three separate projects. The NEPTUNE system is a manned, outer-planetary explorer designed with Jupiter exploration as the baseline mission. The lifetime requirement for both reactor and power-conversion systems was twenty years. The second project undertaken for the power supply was a Mars Sample Return Mission power supply. This was designed to produce 2 kW of electrical power for seven years. The design consisted of a General Purpose Heat Source (GPHS) utilizing a Stirling engine as the power conversion unit. A mass optimization was performed to aid in overall design. The last design was a reactor to provide power for propulsion to Mars and power on the surface. The requirements of 300 kW of electrical power output and a mass of less than 10,000 Rg were set. This allowed the reactor and power conversion unit to fit within the Space Shuttle cargo bay.

Source record↗
DOE OSTI2020

Nuclear Engineering Enrollments and Degrees Survey, 2019 Data (Brief 82)

The 2019 survey includes degrees granted between September 1, 2018 and August 31, 2019, and enrollments for fall 2019. Thirty-four nuclear academic programs were surveyed with all but two programs responding. The enrollments and degrees data include students majoring in nuclear engineering or in an option program equivalent to a major. Some nuclear engineering programs have indicated that health physics option enrollments and degrees are also reported in the health physics enrollments and degrees survey.

99 GENERAL AND MISCELLANEOUS↗
DOE OSTI2020

An Application of ASP in Nuclear Engineering: Explaining the Three Mile Island Nuclear Accident Scenario

Abstract The paper describes an ongoing effort in developing a declarative system for supporting operators in the Nuclear Power Plant (NPP) control room. The focus is on two modules: diagnosis and explanation of events that happened in NPPs. We describe an Answer Set Programming (ASP) representation of an NPP, which consists of declarations of state variables, components, their connections, and rules encoding the plant behavior. We then show how the ASP program can be used to explain the series of events that occurred in the Three Mile Island, Unit 2 (TMI-2) NPP accident, the most severe accident in the USA nuclear power plant operating history. We also describe an explanation module aimed at addressing answers to questions such as “why an event occurs?” or “what should be done?” given the collected data.

Computer Science↗