NJOY21: Next generation nuclear data processing capabilities

Conlin, Jeremy Lloyd; Kahler, Albert C.; McCartney, Austin Paul; Rehn, Daniel A.

doi:10.1051/epjconf/201714609040

Cited by 28 publications

(5 citation statements)

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“…Once the input decks were corrected, assuming that the physical models implemented in the Monte Carlo codes were not source of significant difference in keff values, the keff differences could only be attributed to nuclear data effects, which in turn could be due to differences in the processing of data. Indeed, different tools were used for processing nuclear data: NJOY [4] for MCNP [5], GAIA 1.1 (NJOY) for MORET [6], AMPX [2] for SCALE [7] and PREPRO [8] for COG [9] and it is interesting to know the impact of this step on the keff results.…”

Section: Methodsmentioning

confidence: 99%

International criticality benchmark comparison exercise in support of nuclear data validation

et al. 2023

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The objective of this paper is to present the main results of the keff inter-comparison exercise performed in 2019-2022 by LANL, LLNL, ORNL and IRSN on a set of common benchmarks. The paper includes a description of the methodology to make the inter-comparison, presents the set of selected cases along with the main tendencies that could be at-tributed to nuclear data. In addition, it identifies some issues on the processing and interpretation of nuclear data done by the various codes of the intercomparison.

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Section: Methodsmentioning

confidence: 99%

International criticality benchmark comparison exercise in support of nuclear data validation

et al. 2023

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“…Because of the good agreement between the simulation and experiment at room temperature, the likelihood of a geometry mismatch between the them is low. There could be several other reasons to the disagreement between the evaluations and experiment which could relate to the models used and approximations that might not be valid at such low temperatures or approximations in the processing code NJOY [1] used to prepare the data for MCNP.…”

Section: Neutron Leakage Measurementsmentioning

confidence: 99%

“…This comes after years that this field was dormant with little updates or new ENDF evaluations. Evaluated TSL is based on atomistic calculations that in most cases result in a phonon spectrum that can be processed using a code like NJOY [1] to create the scattering kernel for use in applications. In the evaluation assumptions are made on the material structure and crystalinity thus the experiments are also validating such assumptions by comparing them to real materials.…”

Section: Introductionmentioning

confidence: 99%

Experimental validation of thermal scattering evaluations

et al. 2023

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In order to test the performance of new neutron thermal scattering law (TSL) evaluations it is desirable to have experimental data that is highly sensitive to the TSL and provides high fidelity information on the energy dependent performance of TSL evaluations. Three relevant experiments are discussed including: accurate thermal total cross section measurements, thermal neutron die-away experiments, and neutron leakage experiments. The experimental setups and results are reviewed and examples provided for some moderators including polyethylene, Plexiglas, and YHx. For the experiments preformed thus far, there is generally good agreement between the measured total cross section and simulations using current TSL evaluations, however in certain energy ranges differences were observed. Similarly neutron die-away and leakage measurements for samples at room temperature are in good agreement with data computed from TSLs, however leakage measurements for polyethylene at 29K show discrepancies with TSL evaluations.

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“…The sigma-D values were calculated using NJOY21 [8], a modern nuclear data processing code. This was done automatically using the python3 script, NJOY_DPA.…”

Section: Calculation Of the Damage Pseudo-cross-section (𝝈 𝑫 )mentioning

confidence: 99%

Evaluation of the NSUF Reactor Activation and Damage (RAD) Calculator damage component

Cruz

Gale

2020

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As part of the Combined Materials and Experiment Toolkit (CoMET) project, the Nuclear Science User Facilities (NSUF) developed the Reactor Activation and Damage (RAD) Calculator to be used as a general scoping tool to estimate radiation damage in terms of displacements per atom (DPA) and the resulting radioactivity of materials post-neutron irradiation. The calculator is intended to estimate experimental feasibility and be a helpful tool to scope out irradiation proposals. The damage component of the calculator estimates the DPA produced in a reactor irradiation for a limited set of known materials and guides researchers to potential irradiation facilities from the available NSUF research and test reactors. The calculator is not intended as a replacement for in-depth experimental design and dose calculations represented in the physics Engineering Calculations and Analysis Reports (ECAR). Internal validation studies were performed to compare the damage component of the calculator and a series of INL "as-run" physics ECARs for existing Advanced Test Reactor (ATR) experiments. The accuracy of the calculator was within ±50% of the DPA values in the ECARs with more than 85% of the tests being within ±20%. Based on these results, the damage component of the RAD Calculator can be deployed and expected to competently perform. Future modifications to improve the RAD calculator are recommended:• It is recommended that, prior to the calculator being launched, a cautionary statement be created to make users aware of materials with known challenges that the calculator will not handle (e.g., fissile and fertile material are not considered). • It is recommended for a displacement threshold energy (Ed) correction bias to be considered. (FY 2021) • It is recommended to include aspects of thermal transmutations (e.g., Ni transmutation and the production of helium and hydrogen from the 58 Ni (n,α) and (n,p) reactions).

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NJOY21: Next generation nuclear data processing capabilities

Cited by 28 publications

References 0 publications

International criticality benchmark comparison exercise in support of nuclear data validation

International criticality benchmark comparison exercise in support of nuclear data validation

Experimental validation of thermal scattering evaluations

Evaluation of the NSUF Reactor Activation and Damage (RAD) Calculator damage component

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