Study of plasma sheath associated with communications blackout Final report, Jun. 1963 - Dec. 1966
Bibliography of technical reports on plasma sheath phenomena and communications blackout during vehicle atmospheric reentry
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Bulk Electric System Protection Model Demonstration with 2011 Southwest Blackout in DCAT
Protection equipment modeling is critical to power systems planning and operational studies, it enables more accurate system response when control actions including protection relays and remedial action schemes (RAS) are adequately modeled and assessed. This paper incorporates a generic protection philosophy to the Dynamic Contingency Analysis Tools (DCAT), and demonstrates its effectiveness by modeling 2011 Pacific Southwest Blackout event autonomously.
Bulk Electric System, Protection, Blackout, DCAT↗
The application of MAMMOTH for a detailed tightly coupled fuel pin simulation with a station blackout
The accurate calculation of desired quantities to predict fuel behavior in a nuclear reactor requires the solution of inter linked equations representing different physics phenomena. Traditional fuels performance codes often rely on internal empirical models for the pin power density and a simplified boundary condition on the cladding outer surface. These simplifications are performed because of the difficulty of coupling applications or codes on differing domains and mapping the required data. In this work the MAMMOTH application is employed in the demonstration of an approach that more consistent with first principles, in a simulation that couples the neutronics application Rattlesnake, the thermal fluids application RELAP-7 and the fuels performance application BISON. A single fuel pin was modeled based on the dimensions of a fuel rod from a Westinghouse 17*17 optimized PWR fuel assembly. The simulation consisted of a depletion period of 1343 days, representing three full operating cycles, followed by a station blackout (SBO) event. The fuel rod was depleted with a total pin power of 65.81 kW. After 1343 days the fission power was reduced to zero (simulating a reactor shutdown). Decay heat calculations provided the time-varying energy source after this time. For this problem, Rattlesnake, BISON, and RELAP-7 are coupled under MAMMOTH in a tightly coupled approach. Each system solves its physics on a separate mesh and, for RELAP-7 and BISON, on only a subset of the full problem domain. Rattlesnake solves the neutronics over the whole domain, which includes the fuel, cladding, gaps, water, and top and bottom rod holders. Here BISON is applied to the fuel and cladding with a 2-D axisymmetric domain, and RELAP-7 is applied to the flow of the circular outer water channel with a set of 1-D flow equations. For this work, the mesh on the Rattlesnake side is either be 3-D (for low order PN transport or diffusion) or 2-D axisymmetric (for diffusion). BISON has a matching ring structure mesh for the fuel so both the power density and local burnup are transferred accurately from Rattlesnake. At each depletion time step, Rattlesnake calculates a power density, fission density rate, burnup distribution and fast flux based on the current water density and fuel temperature. These are then mapped to the BISON mesh to perform a fuels performance solution. BISON calculates the fuel temperature and cladding surface temperature based upon the current power density and bulk fluid temperature. RELAP-7 then calculates the fluid temperature, water density fraction and water phase velocity based upon the cladding surface temperature. The fuel temperature and the fluid density are then passed back to Rattlesnake for another neutronics calculation. For this paper, sets of results from the detailed calculation are provided for both depletion and the SBO event. We demonstrate that a detailed simulation akin to first principles can be achieved using MAMMOTH and the various MOOSE application on differing domains. (authors)
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS↗
Electrical Cross-Tie Option and Issues to Cope With Extended Station Blackout
The electrical cross-tie option was proposed to cope with extended station blackout event (Ext-SBO) for Barakah NPP in UAE, the EDG Cross-Tie consider a donor Unit EDG as a power source for an Ext-SBO Unit under specific conditions. The cross-tie option is discussed and the issues related to this option are generated in systematic approach as a part of dependencies between multiple units. The applied approach benefited from the previous classification of the historical occurred events as site risk that has dependencies with an enhancement of the approach by adding the operation dimension to the dependencies risk.
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS↗
Integral Effect Test of ATLAS Facility on Multiple Failure in a Prolonged Station Blackout
Since the Fukushima accident, the design extension conditions (DECs) in a nuclear power plant (NPP) have attracted more importance with respect to nuclear reactor safety, and a consensus has been developed such that these high-risk multiple failure accidents should be revisited from the viewpoint of a reinforcement of the 'defense in depth' concept. In particular, a station blackout (SBO) is one of the most important DECs because a loss of the heat sink without an appropriate accident measure might lead to a core uncovery, core damage, and ultimately, a core meltdown under high pressure. SBO has been recognized to be one of the risk-contributing sequences when combined with additional failure of components such as a reactor coolant pump (RCP) seal leakage or a steam generator tube rupture (SGTR). The RCP seal failure could occur due to a loss of continuous cooling through the seal during SBO. The SGTR during SBO can be a potentially important risk due to the release of the fission product with bypassing the containment boundary. The objective of this study is to experimentally simulate and analyze a prolonged SBO scenario in a thermal hydraulic integral effect test facility, ATLAS. As test items in OECD-ATLAS project, two tests for the SBO condition were conducted with additional failures, that is, a RCP seal failure (A2.1 test) and a SGTR (A2.2 test). In those tests, both the effect of the additional failure on reactor safety and the natural circulation characteristics during prolonged SBO conditions could be investigated. The present test can provide physical insight into the system response during the prolonged SBO scenario combined with the multiple failure.
22 GENERAL STUDIES OF NUCLEAR REACTORS↗
Feedback Control Approaches for Restoration of Power Grids from Blackouts
The automated restoration of power systems with variable energy resources is a timely problem to tackle. Automated restoration advice can support operators in deciding on strategic actions to restore power grids from a blackout with a mix of conventional and renewable generation resources. To this end, this paper frames the restoration process of power grids with solar resources as a nonlinear dynamic model with algebraic constraints in discrete time which is steered by feedback control loops. We discuss two feedback-control strategies based on greedy and reinforcement learning algorithms, and contrast their performance with restoration plans generated by a mixed-integer linear program. We found that the reinforcement learning algorithm infers restoration actions faster than the greedy one. However, the tuning process of the reinforcement learning parameters is slower than for the greedy one.
machine learning↗
Branch-and-Bound algorithm applied to uncertainty quantification of a Boiling Water Reactor Station Blackout
Evaluation of the impacts of uncertainty and sensitivity in modeling presents a significant set of challenges in particular to high fidelity modeling. Computational costs and validation of models creates a need for cost effective decision making with regards to experiment design. Experiments designed to validate computation models can be used to reduce uncertainty in the physical model. In some cases, large uncertainty in a particular aspect of the model may or may not have a large impact on the final results. For example, modeling of a relief valve may result in large uncertainty, however, the actual effects on final peak clad temperature in a reactor transient may be small and the large uncertainty with respect to valve modeling may be considered acceptable. Additionally, the ability to determine the adequacy of a model and the validation supporting it should be considered within a risk informed framework. Low fidelity modeling with large uncertainty may be considered adequate if the uncertainty is considered acceptable with respect to risk. In other words, models that are used to evaluate the probability of failure should be evaluated more rigorously with the intent of increasing safety margin. Probabilistic risk assessment (PRA) techniques have traditionally been used to identify accident conditions and transients. Traditional classical event tree methods utilize analysts’ knowledge and experience to identify the important timing of events in coordination with thermal-hydraulic modeling. These methods lack the capability to evaluate complex dynamic systems. In these systems, time and energy scales associated with transient events may vary as a function of transition times and energies to arrive at a different physical state. Dynamic PRA (DPRA) methods provide a more rigorous analysis of complex dynamic systems. Unfortunately DPRA methods introduce issues associated with combinatorial explosion of states. This study presents a methodology to address combinatorial explosion using a Branch-and-Bound algorithm applied to Dynamic Event Trees (DET), which utilize LENDIT (L – Length, E – Energy, N – Number, D – Distribution, I – Information, and T – Time) as well as a set theory to describe system, state, resource, and response (S2R2) sets to create bounding functions for the DET. The optimization of the DET in identifying high probability failure branches is extended to create a Phenomenological Identification and Ranking Table (PIRT) methodology to evaluate modeling parameters important to safety of those failure branches that have a high probability of failure. The PIRT can then be used as a tool to identify and evaluate the need for experimental validation of models that have the potential to reduce risk. Finally, in order to demonstrate this methodology, a Boiling Water Reactor (BWR) Station Blackout (SBO) case study is presented.
22 GENERAL STUDIES OF NUCLEAR REACTORS↗
Effect of ATF Cr-coated-Zircaloy on BWR In-vessel Accident Progression during a Station Blackout
The deposition of protective coatings on nuclear fuel cladding has been considered as a near-term Accident Tolerant Fuel (ATF) concept that will reduce the high-temperature oxidation rate and enhance accident tolerance of the cladding while providing additional benefits during normal and transient. In this study, the performance of the proposed ATF concept of Cr-coated-Zircaloy is assessed using a generic Boiling Water Reactor MELCOR plant model considering a Short-term Station Blackout (STSBO) scenario. Simulation results indicate that the use of Cr-coated-Zircaloy as cladding and canister material mitigates the core degradation process as compared to the traditional Zircaloy cladding and canister design. The onset of fuel degradation and collapse is delayed by over thirty minutes, and the extent of fuel degradation is reduced. Specifically, the gross in-vessel hydrogen generation decreased by almost a factor of three. Although the eutectic reaction between Cr-coating and Zircaloy could cause an early failure of the coating, the improvement in the delay of fuel degradation is still notable. In addition, a thicker coating is found helpful to obtain additional coping time and to decrease hydrogen generation. In addition to the eutectic formation that may compromise Cr-coated Zr, a different failure mode is identified for the Cr-coated-Zr when compared to Zircaloy; i.e., a complete melt of base material leads to component collapse before the coating is oxidized and consumed. These findings can help the industry focus on productive areas of research and development for accident-tolerant fuel concepts and enhancement of core safety margins.
73 NUCLEAR PHYSICS AND RADIATION PHYSICS↗
Assessment of Pump Coastdown and Reactor Protection Scram Delays during Station Blackout Conditions
This report presents an assessment of the impact of pump coastdown time and reactor protection scram delays for the Versatile Test Reactor (VTR) during Protected Station Blackout (PSBO) conditions. While previous simulations for the VTR assumed centrifugal pumps in the primary system, the current pre-conceptual design uses electromagnetic (EM) pumps. Because there is uncertainty as to what the parameters of the EM pump design will be, this report focuses on the impact of the flow coastdown and the reactor protection scram delay, not on the needs of the pump design. PSBO transient simulations were performed using the SAS4A/SASSYS-1 fast reactor safety analysis code (version 5.2.3). The model used in the simulations is based on the FY18 SAS4A/SASSYS-1 model. A change to the model was made to replace the centrifugal pump model with an electromagnetic pump model with a motor generator as a coastdown mechanism. The results of the PSBO transient simulations were assessed against the criteria used in Reference 2 with an additional 50°C for conservatism to account for uncertainties. The results show that as the delay before scramming the rods increases, the moment of inertia of the coastdown mechanism must increase to satisfy the criteria. By increasing the moment of inertia to extend the flow coastdown, temperatures can be kept below the desired limits with reactor protection scram delays between 3 and 10 seconds.
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS↗
Orchestrating the Restoration of Wind-Dominant Grids from Blackouts (Final Report of Award No. DE-SC0021410)
This is the final report of Award No. DE-SC0021410: “Orchestrating the Restoration of Wind-Dominant Grids from Blackouts.” It: (1) summarizes the technical/scientific accomplishments, (2) lists the publications containing scientific details of the accomplishments, (3) reports several dissemination activities, (4) names new research grants as consequence of this project, (5) lists the project team funded by the project, and (6) concludes the project.
17 WIND ENERGY↗
Vaporization and decomposition kinetics of candidate re-entry blackout suppressants in low-pressure flames
Measurement of thermal accommodation coefficients between liquids and high temperature gases in low pressure reentry communications blackout intervals
Kurzius, S. C.↗
Apollo 6, 7, and 8 blackout test results
S band communication blackout measurements during reentry phases of Apollo 6, 7, and 8 flights
Hager, F. W.↗
Radio blackout alleviation and plasma diagnostic results from a 25000 foot per second blunt-body reentry
Radio blackout alleviation and plasma diagnostic results from 25000 foot per second blunt body reentry
Akey, N. D.↗
Studies of electron attachment for the alleviation of radio communications blackout
Electron removal from reentry flow fields by dissociative attachment for blackout alleviation
Bialecke, E. P.↗
Effects of nonequilibrium ablation chemistry on Viking radio blackout.
The length of the entry blackout period during descent of the Viking Lander into the Mars atmosphere is predicted from calculated profiles of electron density in the shock layer over the aeroshell. Nonequilibrium chemistry plays a key role in the calculation, both in the inviscid flow and in the boundary layer. This is especially true in the boundary layer contaminated with ablation material, for which nonequilibrium chemistry predicts electron densities two decades lower than the same case calculated with equilibrium chemistry.
Evans, J. S.↗
An analysis of communications blackout for Pioneer Venus entry probes
Estimates of the maximum duration of communications blackout are presented for a proposed Pioneer Venus mission involving a multiprobe entry targeted to individual impact sites. Calculations of the inviscid flow about the probes have been made using both finite-rate chemistry and equilibrium chemistry computer codes. Equilibrium boundary-layer calculations including ablation are also presented both with and without the presence of alkali metal contaminants from the heat shield. Methods are described for estimating maximum electron density in the inviscid wake and the recirculation region at the base of the probes. The results presented provide a conservative basis for planning for storage and subsequent telemetry of data during the entry phase of the mission.
Grose, W. L.↗
Global blackout following the K/T Chicxulub impact: Results of impact and atmospheric modeling
Several recent studies have suggested that shock decomposition of anhydrite (CaSO4) target rocks during the K/T Chicxulub impact would have ejected tremendous amounts of sulfur gas into the stratosphere. One of the many potential biospheric effects of this sulfur gas is the generation of a sulfuric acid (H2SO4) aerosol layer capable of causing darkness and severe disruption of photosynthesis for periods of years. In this paper we report the preliminary results of our modeling of shock pressures within the anhydrites and of light attenuation by the H2SO4 aerosol cloud. These models indicate that earlier studies over-estimated the amount of sulfur gas produced, but that more than enough was produced to extend global blackout conditions 4-6 times longer than the approximately 3 month predictions for silicate dust alone.
Pope, K. O.↗
Communication Delays, Disruptions, and Blackouts for Crewed Mars Missions
As NASA continues to develop the Moon2Mars campaign, there are a number of challenges that must be addressed to execute a successful crewed mission to Mars. One of those challenges is delays, disruptions, and blackouts that crew will experience during their mission to Mars, and that is the challenge evaluated in this paper. Our analysis showed that communication delays will vary from 0 to 22 minutes over the course of a mission, peaking while the crew is at or just departed from Mars. The disruptions occur in a similar time frame and can last for several days up to several months, depending on the solar disturbance sensitivity of the communication band being used. The delays and disruptions will have an impact on crewed Mars missions, and determining mitigations is future work to be informed by this analysis.
Katherine T McBrayer↗