Shielding Calculations with the Unstructured Mesh Model of the ORNL’s Second Target Station
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Zavorka, Lukas↗
Engineering topics
Remec, Igor
Publications and source records attributed to Remec, Igor.
Decay Dose Shielding Analysis with Hybrid Unstructured Mesh/Constructive Solid Geometry Monte Carlo Calculation and ADVANTG Acceleration
The Oak Ridge National Laboratory (ORNL) Second Target Station (STS) neutron production facility is an accelerator driven pulsed neutron source that is currently being actively developed at ORNL. The neutrons are produced by proton-induced spallation reactions. A proton beam of 700 kW power is delivered to a spallation target in short, less than 1 µs long pulses, with 15 Hz repetition rate. The spallation target of ORNL STS is a rotating water-cooled tungsten target with tantalum cladding housed in a stainless-steel shroud. It is divided into 21 segments. These segments become highly activated due to spallation reactions or nuclei transmutation by the emitted neutrons. The radioactive nuclides continue to decay after ceasing operation. The decay dose rates generated from the target segments once they are removed from their operational location within the core vessel must be accurately quantified to determine the shielding configurations of remote handling tools and transport casks and to aid in planning maintenance events. To determine the shielding configurations needed for an activated target segment after ceasing operation, both the hybrid unstructured mesh (UM)/constructive solid geometry (CSG) approach that was previously utilized for STS analyses [1] and the ADVANTG code [2] were used. Even though the ADVANTG code does not include UM capability, the utilization of its advanced variance reduction technique was crucial to accelerate the extremely difficult final photon transport calculation in this analysis. This paper also describes the procedures taken to mitigate the convergence issues that occur when ADVANTG uses a source definition that does not match the source of the final Monte Carlo (MC) calculation. These convergence issues often occur because of inconsistencies between source and transport biasing parameters.
Ibrahim, Ahmad↗
Neutronics Calculations with the Unstructured Mesh Model of the ORNL’s Second Target Station
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Zavorka, Lukas↗
A liquid hydrogen tube moderator arrangement for SNS second target station
Liquid hydrogen filled tubes arranged in a triangular shape surrounded by light-water premoderators were investigated as cold moderators coupled to a neutron production zone of a tungsten target fed by a 1.3 GeV proton beam in a short-pulse mode. A moderator concept optimized for the tube length, premoderator thickness, and target position was found to deliver the highest pulse-integrated neutron brightness suitable to send cold neutron beams for neutron scattering instrumentation geared toward medium resolution and small samples. Reducing the tube diameter from 50 to 10 mm boosts the cold neutron brightness (E < 10 meV) by a factor of 2.25, also with enhancements seen by downsizing the height of cylindrical moderators in earlier studies. Attempts were made to characterize this novel moderator system with regard to pulse shapes, local brightness distribution, and angular distribution of emission at the neutron emission port.
Gallmeier, Franz X. (ORCID:0000000171500764)↗
Neutronics Analysis in Preparation of the Blue Room Experiment
The goal of the Blue Room experiment is to investigate the ‘thermal shock’ stress in a tungsten target provoked by proton pulse impact. Short, strong pulses of highly energetic protons cause a rapid energy deposition in tungsten, which leads to a sudden temperature rise. This thermal shock causes a stress response and leads to fatigue, which can limit the lifetime of the target. In the Blue Room experiment, tungsten blocks will be irradiated by pulses of 800 MeV protons with several intensities to gain understanding in the strain response of the tungsten block.
36 MATERIALS SCIENCE↗
Generation of Beamline Sources – Preliminary Design (Second Target Station (STS) Project)
This report provides a short summary of how four neutron beamline sources at the US Department of Energy’s Oak Ridge National Laboratory were generated for use in shielding and activation analysis along Second Target Station (STS) neutron beamlines, inside and outside the bunker, and inside instrument caves. Analysis of these sources shows that an angular acceptance of ±2° from the axis of the neutron beamline is all that is needed to accurately model dose rates for these applications. Further analysis shows that the surface area of the tallies used to calculate these sources, and therefore the number of particles in the sources (normalization), should be scaled up to ~19 × 19 cm to provide conservative estimates of dose rate outside the bunker. The spectrum of neutrons entering beamline 11 (ST11), which has the hardest spectrum at high energies and the most neutrons below 100 eV, produces the largest prompt dose rates inside and outside the bunker and the largest number of activation products inside the bunker, therefore, producing the largest residual dose rates.
46 INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND ↗
Optimization of the moderators in the STS preliminary design
This report details the results for an optimization of the dimensions of the moderators in the preliminary design of the Spallation Neutron Source Second Target Station (STS). This study uses the optimization algorithms of Dakota and an unstructured mesh model for the moderators in MCNP. More details on the unstructured mesh model and the automated mesh generation can be found in [3]. Parallel to this effort, the same moderator geometries have been optimized using a constructive solid geometry (CSG) MCNP model. More details on this model and its results can be found in [4]. Three optimal designs are selected for each moderator: one that is optimized for maximum peak brightness, one for maximum time-integrated brightness, and one for a combination of peak and time-integrated brightness. The backbone of the optimization work flow is provided by Dakota. For each set of design parameters requested by Dakota, a new solid geometry is automatically built in Creo and SpaceClaim, and subsequently exported to Attila4MC to generate an unstructured mesh geometry for MCNP. After the MCNP calculation is finished, the objective function (e.g., brightness metric) is returned to Dakota. After the new design has been evaluated, a result-file is written, and Dakota proposes the next set of design parameters to be evaluated. The loop continues until a specified convergence criterion has been met. The design parameters of the cylindrical (upper) moderator include the hydrogen radius, the premoderator thickness (top, bottom, radial), the beryllium radius and the horizontal position of the moderator. The crucial design choice is the hydrogen radius. A radius of 62 mm is shown to provide the maximum time-integrated brightness. The maximum peak brightness occurs with a radius of 40 mm. A combined (middle) design, which balances peak and time-integrated brightnesses, is obtained with a hydrogen radius of 50 mm. The premoderator thicknesses and the beryllium radius are slightly larger in the design optimized for time-integrated brightness than in the design optimized for peak brightness. The sensitivity to these two parameters is relatively small close to the optimal configurations. The hydrogen vessel and vacuum vessel wall thicknesses are dependent on the radius of the liquid hydrogen due to structural integrity requirements. The increased wall thicknesses for larger vessels significantly penalize the time-integrated brightness, with the maximum obtainable value reduced by more than 10% relative to earlier studies which used fixed vessel wall thicknesses. The impact of the variable wall thicknesses is much less for the peak brightness and combined brightness designs. The design parameters of the tube (lower) moderator selected for the optimization are the tube length, the annular premoderator thickness, the beryllium radius and the horizontal position of the moderator. The tube length is the crucial parameter and is chosen large (210 mm) and small (125 mm) in the designs optimized for time-integrated and peak brightness respectively. A combined optimal design has a tube length of 170 mm. The premoderator thickness and the beryllium radius are chosen larger in the design optimized for time-integrated brightness.
42 ENGINEERING↗
Second Target Station (STS) Project: Analysis of Bunker Shielding–Preliminary Design
At the Department of Energy’s Oak Ridge National Laboratory, the Second Target Station (STS) beamline sources for preliminary design have been used to perform a shielding analysis of the bunker. The simulations in this report used the ST11 beamline source, primarily the ST11 neutron source, because that source provides conservative prompt total dose rate estimates for all beamlines. Prompt total dose rates (i.e., neutron plus photon dose rates when the beam is on) were calculated on top of the bunker roof, outside the bunker wall, and in the basement below the bunker and instrument floor. Design changes were made to ensure the prompt total dose rate in these areas does not exceed 0.25 mrem/h. This report documents the required shielding thicknesses to meet this dose rate limit. There is one exception to this: for a combination of open and closed beamlines, the prompt total dose rate outside the bunker across from the closed beamline, where there is less shielding due to the lack of beamline shielding, slightly exceeds 0.25 mrem/h. A future analysis will document the shielding modifications required to reduce the calculated prompt total dose rates for this configuration to less than 0.25 mrem/h once more details regarding the STS high density concrete density and composition are known. Finally, prompt total dose rates inside the bunker were simulated. The results of this simulation show that the majority of prompt total dose rate in the bunker is due to neutrons, and a few percent of the total is caused by secondary photons created by the neutrons. The contribution to prompt total dose rate inside the bunker by the primary photons that enter each beamline from the target/moderator area is at least two orders of magnitude less than the neutron contribution. This means prompt total dose rate contributions due to primary photons inside and outside the bunker can be neglected.
42 ENGINEERING↗
CINDER90 and CINDER2008 Comparison for Second Target Station Analysis
A preliminary target activation analysis for the Second Target Station (STS) at the Spallation Neutron Source (SNS) located at Oak Ridge National Laboratory (ORNL) was preformed using Monte Carlo N-Particle X (MCNPX), CINDER90, and the corresponding multi-group cross section libraries distributed with CINDER90. This preliminary analysis has been used to guide some design decisions of the STS target design. Using the MCNPX output files from this preliminary analysis, a comparison of the activation analysis using CINDER90 and CINDER2008 was performed. While the CINDER90 code has been validated for use in spallation source activation and transmutation calculations, and compares well with measurements, the transition to the modernized version of the code (CINDER2008) and the updated cross section libraries is desirable. The goal of this comparison is to evaluate the differences and implications for the STS activation analysis. Overall, the total activity differs between CINDER2008 and CINDER90 by no more than 20% for the materials evaluated in this report. The largest discrepancies were observed in the decay gamma intensity densities with CINDER90 calculating a factor of 2 higher than CINDER2008.
97 MATHEMATICS AND COMPUTING↗
Neutron Dose Rate Calculation with the MCNP6 Hybrid Geometry Model of the Second Target Station
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Zavorka, Lukas↗
Neutronics analyses for the conceptual design of the SNS Second Target Station
The Spallation Neutron Source, in operation at the Oak Ridge National Laboratory since 2006, was designed to allow the addition of a second target station and an upgrade of the accelerator proton power. Both upgrades are now underway. Here we describe the evolution of the design of the target of the second target station with the emphasis on the effects of the proton beam footprint on the energy deposition in the target, stresses induced by the pulsed operation, and the importance of the residual heat. The moderator configurations and their optimization are discussed. With the utilization of pure parahydrogen moderators, small neutron beam cross-sections, and the specific optimization, neutron beams of the second target station will achieve exceptionally high peak brightness and time-averaged brightness.
72 PHYSICS OF ELEMENTARY PARTICLES AND FIELDS↗
Experience with Automatic CAD to MCNP Model Conversion at ORNL’s SNS
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Remec, Igor↗
Monte Carlo Neutronics Analysis of the SNS STS Monolith
The neutronics analysis for the Oak Ridge National Laboratory’s Spallation Neutron Source second target station monolith conceptual design was performed entirely with the Monte Carlo method. It has been demonstrated that even though the monolith provides approximately peta-scale attenuation of the dose rates, Monte Carlo simulations are within reach of computing capabilities of relatively inexpensive Linux clusters. Several monolith configurations achieved or exceeded design requirements and provide basis for the final design.
Remec, Igor↗
Radiation-Induced Degradation of Concrete in NPPs
Nuclear power plants life extensions to 60 and potentially 80 years of operation have renewed interest in long-term material degradation. One material being considered is concrete. Swelling of aggregates driven by radiation induced displacements of atoms is currently considered to be the most probable leading contributor to the radiation induced degradation of concrete mechanical properties. In the biological shields of nuclear plants atom displacements are dominated by neutron contributions while gamma-ray contributions are negligible. For a number of minerals, which are common constituents of aggregates, in concrete it was shown that ~95% of the dpa is generated by neutrons with energies above 0.1 MeV. Neutrons with energies above 1 MeV contribute only ~20 to 25% to the dpa. Therefore, if neutron fluence is used as correlation parameter for the concrete degradation, the neutron fluence energy cut-off of 0.1 MeV should be used. Based on the projected neutron fluence values (E > 0.1 MeV) in the concrete biological shields of the US pressurized water reactor fleet and the available data on radiation effects on concrete, some decrease in mechanical properties of concrete cannot be ruled out during extended operation beyond 60 years.
Remec, Igor↗
Neutronics Analyses for the Spallation Neutron Source Second Target Station
The Spallation Neutron Source (SNS) and the High Flux Isotope Reactor (HFIR), two of the word-class neutron scattering facilities, are located at the Oak Ridge National Laboratory. The SNS and HFIR are funded by the U.S. Department of Energy, Office of Science, Office of Basic Energy Science, and are operated as user facilities, available to researchers from all over the world. Currently there are thirteen neutron scattering instruments in operation at the HFIR and twenty at the SNS First Target Station.Producing the cutting edge science requires continuous improvements and development of the facilities and instruments. The SNS was designed from the beginning to allow addition of the Second Target Station (STS), and an upgrade of the accelerator power. At this time both advances: the accelerator upgrade and the construction of the STS are in preparation.Current baseline design for the STS calls for a rotating compact tungsten target. The target station is driven with short (<1 μs) proton pulses at 10 Hz repetition rate and 467 kW proton beam power, and is optimized for high intensity and high resolution long wavelength neutron applications. The proton beam footprint as small as acceptable from the mechanical and heat removal aspects is planned to generate a compact-volume neutron production zone in the target, which is essential for tight coupling of the target and the moderators and for achieving high-intensity peak thermal and cold neutron fluxes. The STS will allow operation of approximately 22 beamlines and will expand and complement the current national neutron scattering capabilities.This paper will present an update of the status of the neutronics analyses performed for the STS and will discuss the performance of the moderators, heating rates, activation analyses, and shielding calculations which provide input in the engineering design.
Remec, Igor↗
HFIR Cold Source Upgrade Options
Several cold source configurations that provide 40% to 90% higher brightness than the reference cold source in broad ranges of wavelengths longer than ~ 2 Å were identified. These CS configurations use hydrogen volumes 2.5 to 4 times larger than the reference source, require a nearly pure para-hydrogen for operation (99% para-hydrogen was assumed in the calculations), and impose heating 1.9 to 2.7 times higher than the reference cold source. Implementation would require adding an ortho-para hydrogen converter and increasing the refrigeration capacity. The brightness increase varies considerably with energy through the cold and thermal neutron range; however, the shapes of the curves of the brightness-increase-versus-energy are very similar for all the configurations analyzed. Up to 2.3 times higher brightness is observed around 3 Å wavelength. The even higher gains of 3.1 at 35 Å are practically of lower interest. Meanwhile, around 1.5 Å a brightness decrease of up to 50% is seen for all but one configuration. The configurations with connected HB-1 and HB-4 beamtubes allow the extraction of neutron beams from both sides of the cold source, therefore effectively doubling the potential number of instruments served, while providing brightness increases in the 40 % to 90 % range. A higher intensity neutron source, which would deliver ~2 times more neutrons down the beamtube, at brightness increased up to 45 %, can be obtained by increasing the radius of the HB-4 and the cold source by ~ 1 cm; which can be realized within the restrictions imposed by the reactor vessel flanges.
47 OTHER INSTRUMENTATION↗
MONTE CARLO NEUTRONICS ANALYSIS OF THE SNS STS MONOLITH
Neutronics analysis for the Oak Ridge National Laboratory Spallation Neutron Source second target station monolith conceptual design was performed entirely with the Monte Carlo method. It has been demonstrated that even though the monolith provides ~peta-scale attenuation of the dose rates, Monte Carlo simulations are within reach of computing capabilities of relatively inexpensive Linux clusters. Several monolith configurations achieved or exceeded design requirements and provide basis for the final design.
Remec, Igor↗
Monte Carlo neutronics analysis of the SNS STS monolith - 25684
Neutronics analysis for the Oak Ridge National Laboratory's Spallation Neutron Source second target station monolith conceptual design was performed entirely with the Monte Carlo method. It has been demonstrated that even though the monolith provides ∼peta-scale attenuation of the dose rates, Monte Carlo simulations are within reach of computing capabilities of relatively inexpensive Linux clusters. Several monolith configurations achieved or exceeded design requirements and provide basis for the final design. (authors)
43 PARTICLE ACCELERATORS↗