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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 127 records · Page 7

Increasing the reliability of the shutdown of 500 - 750-kV overhead lines equipped with shunt reactors in an unsuccessful three-phase automatic repeated closure cycle

The reasons for circuit-breaker failures during repeated disconnection of 500 - 750 kV overhead lines with shunt reactors in a cycle of unsuccessful three-phase automatic reconnection (TARC) are analyzed. Recommendations are made for increasing the operating reliability of power transmission lines with shunt reactors when there is unsuccessful reconnection.

24 POWER TRANSMISSION AND DISTRIBUTION↗

Benchmark specifications for EBR-II shutdown heat removal tests

Argonne National Laboratory (ANL) is hosting an IAEA-coordinated research project on benchmark analyses of sodium-cooled fast reactor passive safety tests performed at the Experimental Breeder Reactor-II (EBR-II). The benchmark project involves analysis of a protected and an unprotected loss of flow tests conducted during an extensive testing program within the framework of the U.S. Integral Fast Reactor program to demonstrate the inherently safety features of EBR-II as a pool-type, sodium-cooled fast reactor prototype. The project is intended to improve the participants' design and safety analysis capabilities for sodium-cooled fast reactors through validation and qualification of safety analysis codes and methods. This paper provides a description of the EBR-II tests included in the program, and outlines the benchmark specifications being prepared to support the IAEA-coordinated research project. (authors)

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS↗

Regulation of the Shutdown Defueling and Decommissioning Reactors in the United Kingdom - 16576

Nuclear policy, including for decommissioning, in the United Kingdom is set by the UK Government. The Nuclear Decommissioning Authority, NDA, is responsible for managing the clean-up of the UK's nuclear legacy which includes the first generation of Magnox power stations. Magnox Ltd (MXL), owned by Cavendish Fluor Partnership, is the licensee and the management and operations contractor responsible for ten Magnox reactor sites and two restoration sites in the UK, working for the sites' owner, NDA. The work of the company is diverse covering electricity generation at Wylfa (until December 2015), defueling, and preparation for an interim end state, known as Care and Maintenance (C and M) which will precede the final site clearance. The C and M phase is expected to last over 75 years during which the sites are maintained in a passively safe and secure state while radiation levels are left to decay naturally. Preparations for this phase include removing fuel from the reactors and storage ponds; retrieving intermediate level waste from current stores and treating it or converting it to forms suitable for long-term storage or disposal and making sure of the integrity of critical safety systems of the de-fuelled reactors. The Decommissioning, Fuel and Waste programme within the Office for Nuclear Regulation, ONR, regulates nuclear safety in the 12 Magnox nuclear licensed sites. ONR works with the environmental regulators who are responsible for environmental protection on nuclear sites. The focus of this paper is the regulation of nuclear safety by ONR across the Magnox sites and the interactions with nuclear security and the environmental aspects required to achieve effective, proportionate and efficient regulation of these sites in the UK. ONR's strategy for regulating the Magnox defueling and decommissioning sites is focused on enabling the licensee to complete the initial stages of decommissioning and reduce the nuclear and radioactive hazards on its sites. To this effect, ONR's revised inspection guidance is centred on inspecting the (remaining) important systems for safety identified in the safety cases. Other interventions focus on engaging with the licensee on safety significant decommissioning projects to gain evidence of the licensee's readiness prior to and during these activities rather than formal assessment of the associated safety cases. In light of reduced hazards and risks across the de-fueled and decommissioning Magnox reactors, ONR's revised regulatory expectation regarding evolution of emergency arrangements during decommissioning is based on key transition points that follow electricity generation. Implementation of these revised strategies as well as organisational restructuring within the team responsible for regulation of the Magnox fleet has resulted in improved efficiency and consistency in regulatory approach whilst securing the required safety standards in managing decommissioning activities. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

Moderation Control Challenges in a Shutdown Facility

On October 27, 2015, an Occurrence Reporting and Processing System (ORPS) Significance Category 1 nuclear criticality safety (NCS) event was discovered at the Paducah Gaseous Diffusion Plant (PGDP) located near Paducah, Kentucky. The NCS violation was a result of the failure to obtain semi-annual moisture samples on sections of large (greater than or equal to 14-inch inside diameter) cascade piping. The event was reported in ORPS EM-PPPOFPDPPGDP- DEAC-2015-0020 under reporting criterion 3C(2) which states, 'A condition in which no documented controls are available to prevent a criticality accident. An accident has not occurred due to other, non-documented barriers or controls.' The purpose of this paper is to present the challenges the site encountered maintaining atmospheric moderation control after the enrichment operation ended, the oversight activities in response to the event and the need to evaluate the changed conditions impact on the Nuclear Criticality Safety Evaluation (NCSE)

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗

The Multi-Step CADIS Method for Shutdown Dose Rate Calculations and Uncertainty Propagation - Paper 137

The Multi-Step Consistent Adjoint Driven Importance Sampling (MS-CADIS) hybrid MC/deterministic method has been proposed to speed up the SDDR MC neutron transport calculation using an importance function that represents the neutron importance to the final SDDR. This paper provides some valuable insights regarding the MS-CADIS method, including physical interpretations of the MS-CADIS adjoint neutron source and the MS-CADIS adjoint neutron flux. The paper also describes the feasibility of using the MS-CADIS adjoint neutron source to calculate the SDDR uncertainty resulting from uncertainties in the MC neutron calculation. A companion paper will provide numerical results that demonstrate the effectiveness of the MS-CADIS method in speeding up SDDR MC simulations and in calculating SDDR uncertainties for problems related to fusion energy systems. (authors)

61 RADIATION PROTECTION AND DOSIMETRY↗

Determination of initial fuel state and number of reactor shutdowns in archived low-burnup uranium targets

This article presents a method for destructive analysis of irradiated uranium (U) targets, with a focus on collection and measurement of long-lived (t 1/2 > ~10 years) and stable fission product isotopes of ruthenium and cesium. Long-lived and stable isotopes of these elements can provide information on reactor conditions (e.g. flux, irradiation time, cooling time) in old samples (> 5–10 years) whose short-lived fission products have decayed away. The separation and analytical procedures were tested on archived U reactor targets at Los Alamos National Laboratory as part of an effort to evaluate reactor models at low-burnup.

37 INORGANIC, ORGANIC, PHYSICAL, AND ANALYTICAL CH↗

Multi-machine analysis of termination scenarios with comparison to simulations of controlled shutdown of ITER discharges

To improve our understanding of the dynamics and control of ITER terminations, a study has been carried out on data from existing tokamaks. The aim of this joint analysis is to compare the assumptions for ITER terminations with the present experience basis. The study examined the parameter ranges in which present day devices operated during their terminations, as well as the dynamics of these parameters. The analysis of a database, built using a selected set of experimental termination cases, showed that, the H-mode density decays slower than the plasma current ramp-down. The consequential increase in f<sub>GW</sub> limits the duration of the H-mode phase or result in disruptions. The lower temperatures after the drop out of H-mode will allow the plasma internal inductance to increase. But vertical stability control remains manageable in ITER at high internal inductance when accompanied by a strong elongation reduction. This will result in ITER terminations remaining longer at low q (q<sub>95</sub>~3) than most present-day devices during the current ramp-down. A fast power ramp-down leads to a larger change in β<sub>p</sub> at the H-L transition, but the experimental data showed that these are manageable for the ITER radial position control. The analysis of JET data shows that radiation and impurity levels significantly alter the H-L transition dynamics. Self-consistent calculations of the impurity content and resulting radiation should be taken into account when modelling ITER termination scenarios. Here, the results from this analysis can be used to better prescribe the inputs for the detailed modelling and preparation of ITER termination scenarios.

70 PLASMA PHYSICS AND FUSION TECHNOLOGY↗

Interpretive MHD modeling of dispersive shell pellet injection for rapid shutdown in tokamaks

Dispersive shell pellet (DSP) injection is modeled with the extended-MHD code NIMROD for interpretive insight into the results of recent DIII-D DSP experiments and to explore the dynamics of an inside-out thermal quench for disruption mitigation in tokamaks. Simulations of the pre-thermal quench (TQ) phase indicate that the upper bound for the quantity of ablated carbon shell material that will not perturb the flux surfaces is in the ballpark of, but somewhat below the experimental quantity. Even below this quantity, sufficient electrons are added to the plasma by the shell material to produce significant dilution cooling before the TQ is triggered. Simulations carried through the end of the TQ have very large amplitude MHD fluctuations (δB/B>10 -2 ) at the time of the plasma current spike associated with current profile redistribution. Finally, after the plasma current spike, which is of comparable amplitude to that measured in DIII-D experiments, none of the runaway electron test-particles whose orbits are tracked throughout the simulation remain confined.

70 PLASMA PHYSICS AND FUSION TECHNOLOGY↗

Process Improvement: Reduce unplanned chlorine delivery shutdowns for the plutonium purification processing [Slides]

Chlorine delivery system used by MET-1 leaked in 2012 and operations were suspended. The existing chlorine gas deliver and detection system is in need of upgrade or replacement. It is reaching the end of the 25 year design life. The current system is a bench scale system that is now running on a continuous basis ~ 10 hours per day. Chlorine is used as a reagent for a number of nuclear material metal preparation and purification applications at LANL Plutonium Facility. MET-1 uses Chlorine for purification. Benefits of improving this process immediately benefit MET-1 who deals with the throughput of Plutonium on the technical and engineering side and benefits NCO-1&2 on the safety side.

37 INORGANIC, ORGANIC, PHYSICAL, AND ANALYTICAL CH↗

Neutronics Benchmark Specifications for EBR-II Shutdown Heat Removal Test SHRT-45R - Revision 1

A neutronics benchmark specification was developed to support the analysis of SHRT-45R test, which was conducted in April 1986 using Experimental Breeder Reactor II (EBR-II) to demonstrate that a sodium-cooled fast reactor (SFR) with a sodium-bonded metallic fuel could be designed such that passive phenomena, as opposed to active electromechanical systems, are effective in protecting the reactor against the potentially adverse consequences of unprotected accidents.

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS↗

Results of Temporary Shutdown Testing and Groundwater Pump-Testing at Agra, Kansas, February-September 2016 and march 2017, and Assessment of Groundwater and Contaminant Migration

In 2005, the Commodity Credit Corporation/U.S. Department of Agriculture (CCC/USDA) conducted a comprehensive investigation of potential contaminant source areas on, and in the vicinity of, the former CCC/USDA grain storage facility in Agra, Kansas (Argonne 2006). The data collected during this investigation identified three primary source areas for carbon tetrachloride contamination. One source is located on the former CCC/USDA property, and the other two (western and eastern) sources are located on adjacent property owned by Pro-Ag Marketing. The soil source located at the western end of the Pro-Ag property has been identified as the sole source of carbon tetrachloride contamination to the groundwater in this portion of the Agra site, and is not associated with any grain storage activities on the former CCC/USDA property. In 2008-2009, to address the carbon tetrachloride contamination detected on its former property, the CCC/USDA initiated source area cleanup as an interim measure (IM). The cleanup employs five large-diameter boreholes (LDBs) that were excavated by auger drilling. The purposes of these borings were to (1) physically remove soils impacted by carbon tetrachloride from the most contaminated area for treatment by onsite land farming and (2) provide locations for the installation of coupled soil vapor extraction (SVE) and air sparging (AS) wells to facilitate in-situ treatment of the carbon tetrachloride in the soils and underlying groundwater. With the approval of the KDHE, operation of the SVE/AS systems began in May 2009, and has generally continued with minimal interruption since that time. Land farming operations to treat contaminated soil excavated from the LDBs were successfully completed in October 2010.

54 ENVIRONMENTAL SCIENCES↗