NCSP FY 2015 AMPX Annual Report

Wiarda, Dorothea; Celik, Cihangir; Williams, Mark L.; Dunn, Michael E.; Daily, Charles R.

doi:10.2172/1567010

Cited by 4 publications

(4 citation statements)

References 6 publications

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“…With the exception of low energy ( 0.1 eV) groups and the first couple of groups, there is less than 8% relative difference between the codes for the energy groups. OpenMC shows good agreement with MCNP results while Shift results show higher show higher relative difference up to 5% with MCNP in the resonance region, which requires further investigation, but it is likely that the difference is due to OpenMC and MCNP using data generated by NJOY [28] and Shift using data generated from AMPX [29].…”

Section: Neutron Flux Spectramentioning

confidence: 92%

ARC reactor neutronics multi-code validation*

2022

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The affordable, robust, compact (ARC) reactor is a tokamak fusion reactor concept currently under development by Commonwealth Fusion Systems (CFS)and Massachusetts Institute of Technology. There are three important neutronics considerations for the operation of the ARC reactor: (1) breeding of enough tritium in the blanket to sustain the D-T reaction in the plasma; (2) ensuring low fluence on the superconducting toroidal field coils; and (3) assessing neutron volumetric heating in structural components. This work aims to perform a validation of the neutronics analysis approach by code-to-code comparison. State-of-the-art software stacks are employed for the neutronics analysis of the ARC reactor, and a computer-aided design (CAD) model is used directly for Monte Carlo (MC) neutron transport calculations. Three software stacks, Attila-MCNP, OpenMC-DAGMC, and Shift-DAGMC, are used to perform neutronic analysesof a 90°sector CAD model of the ARC reactor. Results show that the flux tallies calculated by the three software stacks are very close. Also, the volumetric heatingand tritium breeding values have less than 0.6% relative difference between codes.

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Section: Neutron Flux Spectramentioning

confidence: 92%

ARC reactor neutronics multi-code validation*

2022

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“…AMPX [12] is a collection of computer codes developed at Oak Ridge National Laboratory used to process ENDF-formatted nuclear data files into continuous energy, multi-group, and covariance data libraries for SCALE [13]. AMPX is not included in the NEA processing pipeline scheme illustrated in Fig 1 because the version we employ for processing originates from SCALE-6.2, subject to export control.…”

Section: Ampxmentioning

confidence: 99%

Integrated, Automated, and Reproducible Nuclear Data Processing at the NEA

Foligno,

Holcomb,

Fleming

2024

EPJ Web of Conf.

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Ensuring data preservation is a top priority for the Organization for Economic Co-operation and Development (OECD), Nuclear Energy Agency (NEA) Data Bank. Within this context, “preserving data” encompasses activities such as verifying, processing, sharing, improving, and storing the data. The NEA aims to automate these processes to the greatest extent possible, with the goal of providing the JEFF community with reproducible, high-quality data. To achieve this, the Data Bank has chosen to utilize GitLab, a web-based distributed Version Control System that facilitates the collaboration of different users. The author will present the current progress of the NEA pipeline, an ongoing collaborative initiative aimed at standardizing the processing, verification, and validation of nuclear data.

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“…In addition it was not possible to reuse parts of SAMMY in other projects (e.g., resonance reconstruction, experimental correction), or to implement other fitting routines into SAMMY. The ability to share resonance reconstruction and derivatives of the resonance parameters with respect to cross section with AMPX [2] would be very useful. Because AMPX uses many of the same developers as SAMMY, it is advantageous to share as much code as possible.…”

Section: Modular Designmentioning

confidence: 99%

Modernization efforts for the R-Matrix code SAMMY

Wiarda,

Arbanas,

Brown

et al. 2023

EPJ Web of Conf.

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The R-Matrix code SAMMY [1] is a widely used nuclear data evaluation code focused on the resolved range, which includes corrections for experimental effects. The code is still mostly written in FORTRAN 77 and uses a memory management system suitable for the time of its initial writing in 1984. A modernization effort is underway to update the code to modern software development practices. A continuous-integration testing framework was added to automate the large existing set of test cases. Improvements in memory management were implemented to make the code easier to maintain and enable enhancements. The resonance parameters and covariance information are now stored in C++ objects shared by SAMMY and AMPX [2], which is the processing code that generates nuclear data libraries for SCALE [3]. Further plans include switching to the Evaluated Nuclear Data File (ENDF) reading and writing routines in AMPX because these routines are more robust, easier to maintain, and support more features. Support for the new Generalized Nuclear Database Structure (GNDS) format [4] is also of interest. GNDS will share not only the resonance parameters but also the parameters associated with experimental correction in GNDS. The data are currently available in a binary SAMMY format, and the ability to export them to GNDS would make them more widely available and shareable. The next step will be to use the same resonance processing code at 0K in AMPX and SAMMY as an available formalism. Then, any improvements in the formalism can immediately be tested in SCALE because the reconstruction in AMPX will use the same cross section model. The new data library can then be used for testing using the VALID Benchmark suite [5] or other suitable benchmark suites.

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NCSP FY 2015 AMPX Annual Report

Cited by 4 publications

References 6 publications

ARC reactor neutronics multi-code validation*

ARC reactor neutronics multi-code validation*

Integrated, Automated, and Reproducible Nuclear Data Processing at the NEA

Modernization efforts for the R-Matrix code SAMMY

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