Code Validation Research Articles

Complex heat transfer analysis in heat exchanger with constructal cylindrical fins

This paper documents a 3-D numerical analysis and theoretical prediction in novel micro-channel heat sinks comprise of three configurations. The first design has solid fins, the second model has half-hollow fins placed on micro-channel, while in the third design, hollow fins are mounted on the heat sink. The objective of the study is to maximise the dimensionless thermal conductance subject to fixed volume. A microelectronic device released high-density heat flux at the bottom of heat sink and liquid of Reynolds number range between 400 and 500, is applied at entrance of the boundary under laminar forced convection scheme to dispel heat deposited in the cooling channels and the internal parts of the hollows. A multi-objective broadscale step-by-step code is used to perform the optimisation and the results shows that the micro-channel with full-hollows has the highest thermal conductance at Rew<475, followed by solid fins before half-drilled fins. Theoretical analysis is conducted on the three configurations using the intersection of asymptotes method, and the results compared favorably with numerical solution. The findings indicate that the theoretical solution tends to over-predict the numerical results within a certain range of Bejan number. Code validation is performed, and the results align with existing literature.

Analysis of Nanofluid Flow Over a Heated Circular Cylinder using the Volume of Fluid (VOF) Approach

This study employs a two‐phase Volume of Fluid (VOF) model to investigate the flow and heat transfer characteristics of Al₂O₃-water nanofluid over a heated circular cylinder at a Reynolds number of 100. Nanoparticle volume fractions (Φ) ranging from 1% to 10% were analyzed. A comprehensive grid-independence study and code validation were conducted to ensure the accuracy of the results. Increasing (Φ) from 0% to 10% led to significant changes in flow parameters: the mean drag coefficient increased by 27.8% (from 1.33 to 1.7), the fluctuating lift coefficient rose by 56.5% (from 0.23 to 0.36), and the Strouhal number increased by 6.7% (from 0.164 to 0.175). Heat transfer enhancement was observed with increasing nanoparticle concentration, as evidenced by the local Nusselt number at the front stagnation point (θ = 0°) rising by approximately 40% over the same (Φ) range. The study revealed significant changes in pressure distribution around the cylinder, with higher (Φ) values smoothing the pressure gradient and altering the separation point. Time-averaged temperature contours demonstrated more uniform thermal distributions and reduced wake sizes at higher (Φ) values, indicating improved thermal diffusion and heat transfer efficiency. The (VOF) model successfully captured complex two-phase flow dynamics, revealing asymmetric nanoparticle distributions in the wake region at higher concentrations. These findings have important applications in thermal management systems, including electronic and energy systems, potentially leading to more efficient cooling systems and heat exchangers.

Verification and Validation of the VANGARD Pinwise Nodal Code with Analyses of BEAVRS

This paper validates the graphical processing unit (GPU)–based pinwise nodal core calculation code VANGARD using the Benchmark for Evaluation And Validation of Reactor Simulations (BEAVRS), focusing on hot-zero-power (HZP) physics tests, hot-full-power (HFP) depletion, and load follow operation for both Cycles 1 and 2. Results are compared with measured data and other high-fidelity numerical solutions. In HZP physics tests, the critical boron concentration (CBC), control rod bank worth, and isothermal temperature coefficient agree well with measured data, satisfying the design review criteria for typical zero power physics tests. Pin power distributions for various rodded cases confirm the high accuracy of pin-resolved solutions compared to other numerical results. For HFP depletion, CBC closely matches measured data and other high-fidelity numerical solutions, showing differences smaller than 35 and 10 ppm, respectively, throughout the whole depletion steps. Computational performance analysis reveals that a cycle depletion of a realistic pressurized water reactor core can be completed within 3.5 min using a single gaming GPU, which affirms the feasibility of practical pinwise core designs.

Built-in physics models and proton-induced nuclear data validation using MCNP, PHITS, and FLUKA – Impact on the shielding design for proton accelerator facilities

The MCNP, PHITS, and FLUKA are general-purpose Monte Carlo (MC) radiation transport codes that are widely used for many real-world shielding problems at accelerator facilities around the world. Nuclear interactions are described in these codes by either built-in physics models, or tables with evaluated cross sections and secondary energy-angular distributions, or a combination of both. Over the decades, many code validation efforts have been made, owing to the availability of shielding benchmarks to test the physics models and nuclear data and to verify the accuracy of simulation codes.For high beam energy and high beam current accelerator applications, neutron emission through the vacuum pipe along the reverse direction of incident proton beam is an important factor for a shielding design in order to correctly assess the dose rates for workers and the structural materials of the accelerator and handle with the waste activated by the backscattered neutron fluxes. In this work, neutron-production cross sections and thick-target yield predictions from MC codes relying on physics models and nuclear data libraries are benchmarked against the experimental data, in order to assess their accuracy in predicting neutron emission and furthermore to assess the corresponding impact on shielding design.The results of this study demonstrate that the nuclear data libraries and physics models, which are not expected to give good results at lower energies (< 150 MeV) but are used anyhow when there is no nuclear data available or above the energy range where the data tables end in the so-called “mix-and-match” strategy, need further improvements. Among the investigated proton induced nuclear data libraries, JENDL-4.0/HE produces the most satisfactory agreement to experimental data for all target materials, but may still benefit from refinement. Concerning the physics models of the codes, FLUKA V4-4.0 has the best performance in terms of reproducibility of the experimental values. It is also shown that all discrepancies between the calculations and the experiments for the energy range < 10 MeV (which is dominant on the dose rates through the shield thickness), are up to factor of two. This might be considered as an acceptable figure as it is equivalent to a normal safety margin (x2) considered in shielding calculations of accelerator facilities around the world.

THOR: inclusion of charge carriers’ creation and transport in semiconductor detectors in the PENELOPE Monte Carlo simulation code

This study introduces the simulation framework THOR, which was designed to include the creation and transport of electrons and holes in pixelated semiconductors detectors used for x-ray imaging in the PENELOPE v. 2014 Monte Carlo code and its penEasy v.2015 extension. Following the simulation of radiation transport and energy deposition in the detector, the THOR code breaks down into electron-hole pair (EHP) creation, transport, trapping, and modes of detection, including simulations of energy integrating and photon counting detectors. Validation of the THOR code was conducted using the ARTEMIS code. This study shows the impact of the simulation parameters (detector geometry, photon energy, charge carrier dispersion, etc.) on the detector performance metrics. Notably, the energy cut-off for electrons and photons were found to significantly influence accuracy and computational speed, with the identification of the optimal value as 250 eV for improved computational performance without sacrificing accuracy. The ability to adjust the energy necessary to create an EHP specifically for a-Se sensors introduce a novel approach to balancing speed and accuracy effectively. Moreover, the THOR code allows the user to choose the bias direction and which charge is collected, showing the code’s adaptability across various operational scenarios and materials. For instance, the results showed that using a negative bias and collecting holes results in less spatial resolution because the charge would have to travel a longer distance to be collected. Moreover, the trapping is also a factor, since the and the probability of trapping increases with the distance traveled by the charge carrier. The inclusion or exclusion of charge trapping in simulations can significantly influence the detector efficiency, with differences up to 60%. Analysis of physical parameters such as photon energy, detector thickness, composition, and applied electric field provides insights into their effects on detector performance metrics. Understanding these effects is essential for optimizing imaging systems for specific applications, thereby advancing diagnostic capabilities and patient care in medical imaging. In summary, this study offers a comprehensive understanding of detector behavior and simulation optimization, aiming to enhance imaging techniques.

The Effect of Entropy Waves Features on the Indirect Noise Generation within an Aeronautical High-Pressure Turbine stage

Abstract First stages of aeronautical high-pressure turbine are subjected to inlet distortions generated by the combustor systems. Such disturbances, characterized by velocity and temperature fluctuations, are referred to as vorticity and entropy waves and they are convected downstream by the main flow. Such disturbances interact with the turbine stages affecting the stage efficiency, heat exchange and generating noise emissions. This work summarizes a comprehensive numerical campaign on the effect of different Entropy Waves features (i.e. radial position, clocking and swirl direction) on the indirect noise generation of engine-representative high pressure turbine stage tested at the Politecnico di Milano LFM (Laboratory of Fluid Dynamics of Turbomachinery). The numerical campaign is based on URANS CFD simulations with time-varying inlet distortions, carried out with the University of Florence in-house TRAF code. A Discrete Fourier Transform (DFT) based post-processing tool has been used to extract the low frequency entropy wave content to assess indirect noise emissions. The extensive validation of the TRAF code in previous campaigns grants the fidelity of the results in terms of aerodynamic and acoustic quantities. The numerical results provide a deeper insight of the effect of entropy waves features on indirect noise generation. The outcome of the results may be used by the designer to better understand the combustor-turbine interaction, also considering the possible introduction of innovative fuels such as hydrogen or Sustainable Aviation Fuel (SAF).

A Review of Comprehensive Guidelines for Computational Fluid Dynamics (CFD) Validation in Solar Chimney Power Plants: Methodology and Manzanares Prototype Case Study

This review provides a comprehensive examination of CFD modeling procedures for SCPP, with an emphasis on the detailed methodologies and a case study of the Manzanares prototype in Spain. The introduction delineates the historical context and physical modeling principles of solar chimneys, while highlighting their potential in industrial applications. The governing equations are meticulously discussed, covering assumptions in both 2D and 3D CFD modeling, the continuity and momentum equations, and the selection and accuracy of turbulence models, particularly the k-ε equations. The review also delves into heat transfer modeling, encompassing the energy equation and radiation modeling. Analytical evaluations of turbine pressure drop ratios and performance metrics for power generation efficiency are critically analyzed. The establishment of boundary conditions in solar chimney applications, including sky temperature assessments and distinctions between 2D and 3D boundary conditions, is extensively explored. Mesh generation techniques for both 2D and 3D CFD models are presented, supported by case studies. Parametric studies and experimental investigations are scrutinized to elucidate their impact on the performance of solar chimneys. The temperature–entropy diagram for an idealized Brayton cycle is introduced as a conceptual framework for efficiency analysis. Validation of the CFD codes, both 2D and 3D, against experimental data is performed to ensure model accuracy. The review further examines energy balance approaches in modeling solar chimneys, presenting state-of-the-art CFD results and discussing their implications in both 2D and 3D contexts. The synthesis of these findings culminates in a comprehensive conclusion, offering insights into the future directions and potential advancements in the CFD modeling of solar chimneys. This work aims to serve as a definitive reference for researchers and practitioners in the field, providing a robust foundation for the development and optimization of SCPP technology.

Utilizing numerical techniques for modeling radiating Casson nanofluid flow with thermophoretic phenomenon on a heated stretching surface

This work aims to use mathematical modeling to investigate the mechanics of heat and mass transport in dissipative Casson nanofluid flows over a linear rough sheet. This study considers various elements such as thermal radiation, magnetic fields, heat generation, the varied properties of porous media, and the thermophoretic impact. Besides that, it looks into the variations in viscosity, diffusivity, and thermal conductivity, as well as the energy dissipation from viscous internal friction and fluid temperature modifications. The method involves coming up with and changing the boundary layer equations into a group of linked nonlinear ordinary differential equations that use variables that do not have any dimensions. The foundation of the solution strategy for these equations is the Hermite collocation method (HCM), which is renowned for its precision and adaptability. It offers an organized approach to solving the complex differential equations, allowing for accurate numerical solutions. The use of graphical representations ensures thorough data analysis and clarity, while also providing insightful information about the computed outcomes. The code validation method uses numerical comparisons with recent research to confirm the algorithm’s accuracy and dependability, as well as its resilience in comparison to the existing literature. Important conclusions from the study show that thermal boundary layers and nanofluid velocity decrease with increases in the porosity parameter, slip parameter, and magnetic field parameter.

Exploring Allied Health Professionals’ Perceptions and Practice Regarding Recommendations for Intensity of Multidisciplinary Therapy for Stroke Patients: A Qualitative Study

Abstract Background Stroke is a leading cause of death and disability in Ireland; approximately 7,500 Irish people have a stroke every year. Rehabilitation is a key aspect of stroke care; greater amounts of therapy are associated with better recovery. Data from the Irish National Office of Clinical Audit shows that stroke survivors often do not receive recommended amounts of therapy. The recently updated UK and Ireland stroke clinical guidelines now recommend larger amounts of therapy time. This qualitative study explored how allied health professionals (AHPs) feel about the recommendation, and what methods they employ in working to achieve recommended amounts of therapy. Methods This study used a qualitative research design employing semi-structured interviews to collect data. Participants were AHPs working in stroke care in Dublin, Ireland, and were recruited using a combination of purposive and snowball sampling. Interviews were audio-recorded, transcribed, and analysed using the Braun and Clarke six-step thematic analysis method. An external validator was utilised for code and theme validation. This research was approved by the Royal College of Surgeons in Ireland Research Ethics committee. Results Two main themes emerged: ‘Barriers and enablers to achieving guideline recommended therapy time’ and ‘methods of increasing therapeutic time’. Patient factors and clinical resources impact on the provision of therapy post-stroke. Overall, participants felt positive about the recent guideline recommendation for increased therapeutic time. Various methods are employed to augment patient therapeutic time, including technology and semi-supervised practice. Therapy assistants play an important role in achieving greater amounts of therapy. Conclusion AHPs see the new recommendation as challenging but are generally keen to try and achieve it, citing benefits of increased therapy time for patient outcomes. AHPs utilise a wide range of methods to optimise therapeutic time for stroke patients. The role of therapy assistants in supporting delivery of larger amounts of therapy time warrants further evaluation.

Validation methods in modelling the PANDA IPSS experiment: A MELCOR 2.2 assessment of a passive isolation condenser

Nuclear power plants (NPPs) are becoming increasingly interesting for future energy supply. Nowadays, most of the modern NPPs, such as Generation III+ and Small Modular Reactors (SMRs), offer an even higher safety standard than their predecessors, often relying on passive systems. Due to the continuous improvement of design and safety solutions in the nuclear field, it is essential to simultaneously increase modelling capabilities. This can be achieved by the advancement of modelling tools and by increasing the experience of the analyst. This work focuses on code validation to potentially allow users to gain modelling experience and to provide insights for further code development. Due to the complexity of severe accidents, it may prove to be challenging to model passive systems under such conditions, thus the validation is especially important for numerical codes, such as MELCOR.Codes used for the simulation of severe accidents are simplified in order to be capable of capturing all occurring phenomena in a realistic computational time frame. Thus, it is not trivial if these codes are capable of modelling the combination of passive safety systems within the new integrated features present in many NPP designs. For this reason, this work aims to investigate how such assessments should be performed as well as to consider the severe accidents code MELCOR with respect to the simulation of a passive isolation condenser at the large-scale experimental facility PANDA with and without the presence of non-condensable gases.Our work summarises the present ideas with regards to validation and verification of nuclear codes and highlights the fact that the severe accident code MELCOR is capable of simulating passive safety systems, such as the passive isolation condenser. Improvements can be made when modelling condensation in the presence of non-condensable gases and thus suggestions were made for the improved modelling.

Validation of anorexia nervosa and Bulimia nervosa diagnosis coding in Danish hospitals assisted by a natural language processing model

IntroductionThe Danish Health Care Registers rely on the International Statistical Classification of Diseases and Related Health Problems (ICD)-classification and stand as a widely utilized resource for health epidemiological research. Eating disorders are multifaceted syndromes where two distinctive diagnoses are defined, anorexia nervosa (AN) and bulimia nervosa (BN). However, the validity of the registered diagnoses remains to be verified. Manuel chart review is often the method for validation of diagnosis codes, but there is limited research on how natural language processing (NLP) models could enhance this process. ObjectiveTo investigate the accuracy of the clinical use of ICD-10 diagnosis codes F50.0, F50.1, F50.2, and F50.3 in the Danish Health Care Registers, using a manual chart review assisted by NLP. MethodFrom a cohort of all individuals attending hospitals in Region of Southern Denmark with registered electronic health information, we extracted medical information from the electronic health journal on 100 individuals with each of the four diagnosis codes. After extraction, an NLP model with regular expression search patterns identified relevant text passages for manual chart review. ResultsOverall, 372 of the 400 diagnosis codes (93%) were correct. A diagnosis code for AN was correct in 90% of instances, 96% for atypical AN, 96% for BN and 90% for an atypical BN diagnosis code. ConclusionWe found that the accuracy of a diagnosis code F50.0, F50.1, F50.2, and F50.3 to be high. This confirms that the generally well-documented validity of the Danish health care registers also applies to the eating disorder diagnoses.

Verification and Demonstration of One-Dimensional Freezing Model in SAM for Salt-Cooled Reactor Analysis Applications

This work presents the development and implementation of the one-dimensional freezing model in system analysis code SAM (System Analysis Module), code verification using analytical solutions, and code demonstration of a postulated overcooling transient for a fluoride salt–cooled high-temperature reactor (FHR) system and safety analysis applications. This paper first summarizes the freezing model, finite element numerical method, and special numerical treatment for handling transitions between single- and two-phase conditions. Analytical solutions are derived for two cases, with and without solid walls, for code verification purposes. As expected, the numerical results predicted by SAM agree very well with the analytical solution. A code demonstration is then performed on a postulated protected overcooling transient event of a generic reference pebble bed FHR design. The code was found to successfully predict salt freezing during such a postulated event. However, due to the lack of salt freezing testing data, code validation is not performed in this work, but will be pursued in future studies when such data become available.

Validation of the FLUKA code to simulate response functions of organic liquid scintillator for high‐energy neutrons

In this research, the FLUKA code was employed to calculate the response functions of the BC501A organic scintillation detector for energies ranging from 25 to 800 MeV. Using the AUXSCORE, EVENTBIN and TCQUENCH cards, the response function of the BC501A organic scintillation detector to mono-energetic neutrons in the energy range of 25–800 MeV was computed. The comparison confirms that the simulation results obtained from the FLUKA code show a promising agreement with the results obtained from experiments, other codes, and the analytical method.

53226 Validation of keratinocyte carcinoma diagnosis and treatment codes among veterans with HIV

53226 Validation of keratinocyte carcinoma diagnosis and treatment codes among veterans with HIV

Overview of T and D–T results in JET with ITER-like wall

Abstract In 2021 JET exploited its unique capabilities to operate with T and D–T fuel with an ITER-like Be/W wall (JET-ILW). This second major JET D–T campaign (DTE2), after DTE1 in 1997, represented the culmination of a series of JET enhancements—new fusion diagnostics, new T injection capabilities, refurbishment of the T plant, increased auxiliary heating, in-vessel calibration of 14 MeV neutron yield monitors—as well as significant advances in plasma theory and modelling in the fusion community. DTE2 was complemented by a sequence of isotope physics campaigns encompassing operation in pure tritium at high T-NBI power. Carefully conducted for safe operation with tritium, the new T and D–T experiments used 1 kg of T (vs 100 g in DTE1), yielding the most fusion reactor relevant D–T plasmas to date and expanding our understanding of isotopes and D–T mixture physics. Furthermore, since the JET T and DTE2 campaigns occurred almost 25 years after the last major D–T tokamak experiment, it was also a strategic goal of the European fusion programme to refresh operational experience of a nuclear tokamak to prepare staff for ITER operation. The key physics results of the JET T and DTE2 experiments, carried out within the EUROfusion JET1 work package, are reported in this paper. Progress in the technological exploitation of JET D–T operations, development and validation of nuclear codes, neutronic tools and techniques for ITER operations carried out by EUROfusion (started within the Horizon 2020 Framework Programme and continuing under the Horizon Europe FP) are reported in (Litaudon et al Nucl. Fusion accepted), while JET experience on T and D–T operations is presented in (King et al Nucl. Fusion submitted).

The MUSIC Critical Benchmark and Nuclear Data

The Measurement of Uranium Subcritical and Critical (MUSIC) experiment was a series of measurements of critical and subcritical configurations of bare highly enriched uranium. The goal was to compare measurement methods, analysis techniques, and simulation methods across regimes of criticality and to provide high-quality validation of 235U nuclear data. A benchmark evaluation of the two critical configurations of the MUSIC experiments will soon be published in the release of the International Criticality Safety Benchmark Evaluation Project Handbook. The recent execution of the experiment aids in proper quantification of model simplifications and all uncertainties associated with the experiment. Historical benchmark evaluations are heavily relied on for uranium nuclear data validation despite the fact that the same level of documentation and comparable uncertainty analysis may not be present. The MUSIC evaluation is less likely to include “unknown unknowns” that could impede accurately modeling the system. Presented are both highly detailed and very simplified models, which represent the experimental configurations accurately, aiding the users of the benchmark for nuclear data or transport code validation. The sensitivities of k eff to nuclear data and nuclear data–related uncertainties are very similar between this experiment and previous bare uranium sphere experiments. In addition, the nuclear data uncertainties to any nuclides other than 235 U are small. For all these reasons, the recently evaluated MUSIC benchmark critical configurations could prove very useful for 235 U nuclear data validation. Currently, major libraries have good agreement with the experimental results, within 200 pcm for all nuclear data libraries, and within one standard deviation of the experimental result for most. Suggested nuclear data adjustments based on MUSIC and Lady Godiva are also presented, with posterior improvements to both the agreement in k eff and the uncertainty associated with the nuclear data.

Development and validation of ARSAC-CORTH coupling code based on a generic coupling architecture

Development and validation of ARSAC-CORTH coupling code based on a generic coupling architecture

The Multiple Roles of Structured Multipurpose Databases in Fusion Research

Most databases in fusion research are devoted to a single topic, such as energy confinement, H-modes, profiles, or disruptions. To allow for a wider range of analysis, modeling, and validation tasks, the JETPEAK broad-based multipurpose database has been developed for JET. This database currently includes 27 065 stationary state (∂/∂t ≈ 0) samples and nearly 1000 scalar, one-dimensional (profiles), and two-dimensional (R and Z dependent) variables grouped into topical structures. A similar database has been created for the Tokamak à Configuration Variable (TCV), comprising 65 000 samples reaching back to early TCV operation in the 1990s. The breadth and flexibility of these databases allows them to be used for a wide variety of investigations such as modeling tasks, confinement scaling, testing, validation and benchmarking of algorithms and modeling codes, and long-term monitoring of device conditions, as well as for documentation.

Upgrade of the Lyman-alpha diagnostic system on DIII-D for main chamber edge neutral studies.

The LLAMA (Lyman Alpha Measurement Apparatus) pinhole camera diagnostic had previously been deployed on DIII-D to measure radial profiles of the Lyman-α (Ly-α) deuterium neutral line brightness across the plasma boundary in the lower chamber to infer neutral deuterium density and ionization rate profiles. This system has recently been upgraded with a new diagnostic head, named ALPACA, that also encloses two pinhole cameras and duplicates the LLAMA views in the upper chamber. Similar to LLAMA, ALPACA provides two times 20 lines of sight, viewing the plasma edge on the inboard and outboard sides with a radial resolution of ∼2.5 cm (FWHM) and an effective time resolution of ∼1 ms that allows for the investigation of inter-ELM dynamics. The extended Ly-α system provides better coverage to study neutrals in experiments with various plasma shapes utilizing both the upper and lower divertors. Furthermore, post-campaign calibration of the LLAMA diagnostic has successfully been demonstrated for the first time. This was facilitated by various upgrades to the calibration set-up and detailed measurements of the emissivity distribution of the Ly-α calibration source using a pinhole collimator. It was found that the sensitivity of the inboard LLAMA pinhole camera was reduced by a factor of 2.0 ± 0.2 over the course of six months of plasma operation in 2021. The upgraded Ly-α system, equipped with improved absolute calibration, will provide key input for neutral fueling and pedestal particle transport studies and for 2D edge transport code validation on the DIII-D tokamak.

Development of a phenomena identification and ranking table (PIRT) for intermediate break loss-of-coolant accident in PWRs

Recent safety issues such as cladding oxidation and fuel fragmentation, relocation and dispersal (FFRD) make the loss-of-coolant accident (LOCA) acceptance criteria more difficult to be satisfied. To obtain the adequate safety margin and more economical use of the nuclear power plant, re-classification of LOCAs for Korean operating PWRs is now under consideration to exclude the large break LOCA (LBLOCA) from the design basis accidents (DBAs). Therefore, the intermediate break LOCA (IBLOCA) might become the limiting break size of concern in the LOCA analysis. To accomplish this reform of LOCA classification, an extensive understanding of IBLOCA is crucial, and the applicability of safety analysis code should be confirmed. For this purpose, IBLOCA PIRT was developed. The PIRT panel was organized and the general process of the PIRT development established by Wilson and Boyack (1998) was adopted to develop the IBLOCA PIRT. Based on IBLOCA analyses using the safety and performance analyzing code (SPACE), the PIRT panel defined the temporal phases, systems, components and possible phenomena during an IBLOCA. For all possible phenomena, the relative importance and the knowledge level were determined for each component and each phase via discussions among PIRT panel members. For phenomena having relatively high importance, a code validation matrix was also developed. The results of the IBLOCA PIRT will be used to improve the SPACE code for IBLOCA application and resolve future regulatory issues.