cometadata/datacite-titles-descriptions-related-identifiers huggingface dataset:
DOI: 10.6084/m9.figshare.18467523
title: Improvements in the particle and heavy-ion transport code system (PHITS) for simulating neutron-response functions and detection efficiencies of a liquid organic scintillator

description: In this study, we simulated the neutron-response functions and detection efficiencies of a liquid organic scintillator using the particle and heavy-ion transport code system (PHITS). We incorporated the algorithm and database of the neutron-response simulation code SCINFUL–QMD into PHITS. Then, we updated the total, elastic, and inelastic cross-section data of the hydrogen and carbon nuclei for neutrons and developed a new scorer to analyze the light outputs from a scintillator. The calculation results of the neutron-response functions and the detection efficiencies were compared with results of SCINFUL–QMD, the previous PHITS with the new scorer, and the reported measurements. It was found that the improved PHITS successfully reproduced the results calculated by SCINFUL–QMD, except for around 150 MeV where a discontinuity in the detection-efficiency curve was observed in the SCINFUL–QMD values. Our results showed better agreement with the measured data than the results of the previous PHITS. The uncertainties of the detection efficiencies calculated by PHITS using the present extensions were estimated to be approximately 15% for neutrons in the energy region below 100 MeV.
DOI: 10.6084/m9.figshare.18467523.v1
title: Improvements in the particle and heavy-ion transport code system (PHITS) for simulating neutron-response functions and detection efficiencies of a liquid organic scintillator

description: In this study, we simulated the neutron-response functions and detection efficiencies of a liquid organic scintillator using the particle and heavy-ion transport code system (PHITS). We incorporated the algorithm and database of the neutron-response simulation code SCINFUL–QMD into PHITS. Then, we updated the total, elastic, and inelastic cross-section data of the hydrogen and carbon nuclei for neutrons and developed a new scorer to analyze the light outputs from a scintillator. The calculation results of the neutron-response functions and the detection efficiencies were compared with results of SCINFUL–QMD, the previous PHITS with the new scorer, and the reported measurements. It was found that the improved PHITS successfully reproduced the results calculated by SCINFUL–QMD, except for around 150 MeV where a discontinuity in the detection-efficiency curve was observed in the SCINFUL–QMD values. Our results showed better agreement with the measured data than the results of the previous PHITS. The uncertainties of the detection efficiencies calculated by PHITS using the present extensions were estimated to be approximately 15% for neutrons in the energy region below 100 MeV.
DOI: 10.6084/m9.figshare.19692034
title: EXFOR-based simultaneous evaluation of neutron-induced uranium and plutonium fission cross sections for JENDL-5

description: The neutron-induced fission cross sections were simultaneously evaluated for the JENDL-5 library for <sup>233,235</sup>U and <sup>239,241</sup>Pu from 10 keV to 200 MeV and for <sup>238</sup>U and <sup>240</sup>Pu from 100 keV to 200 MeV. Evaluation was performed by least-squares fitting of Schmittroth’s roof function to the logarithms of the experimental cross sections and cross section ratios in the EXFOR library. A simultaneous evaluation code SOK was used with its extension to data in arbitrary unit. The outputs of the code were adopted as the evaluated cross sections without any further corrections. The newly obtained evaluated cross sections were compared with the evaluated cross sections in the JENDL-4.0 library and the IAEA Neutron Data Standards 2017. The evaluated cross sections were also validated against the californium-252 spontaneous fission neutron spectrum averaged cross sections, ΣΣ (coupled thermal/fast uranium and boron carbide spherical assembly) neutron spectrum averaged cross sections, and small-sized LANL fast system criticalities. The changes in the obtained evaluated cross sections from those in the JENDL-4.0 library are within 4% (<sup>241</sup>Pu), 3% (<sup>233</sup>U, <sup>240</sup>Pu), or 2% (<sup>235</sup>U, <sup>239</sup>Pu). The newly evaluated <sup>235</sup>U, <sup>238</sup>U and <sup>239</sup>Pu cross sections agree with the IAEA Neutron Data Standards 2017 within 2% with some exceptions.
DOI: 10.6084/m9.figshare.19692034.v3
title: EXFOR-based simultaneous evaluation of neutron-induced uranium and plutonium fission cross sections for JENDL-5

description: The neutron-induced fission cross sections were simultaneously evaluated for the JENDL-5 library for <sup>233,235</sup>U and <sup>239,241</sup>Pu from 10 keV to 200 MeV and for <sup>238</sup>U and <sup>240</sup>Pu from 100 keV to 200 MeV. Evaluation was performed by least-squares fitting of Schmittroth’s roof function to the logarithms of the experimental cross sections and cross section ratios in the EXFOR library. A simultaneous evaluation code SOK was used with its extension to data in arbitrary unit. The outputs of the code were adopted as the evaluated cross sections without any further corrections. The newly obtained evaluated cross sections were compared with the evaluated cross sections in the JENDL-4.0 library and the IAEA Neutron Data Standards 2017. The evaluated cross sections were also validated against the californium-252 spontaneous fission neutron spectrum averaged cross sections, ΣΣ (coupled thermal/fast uranium and boron carbide spherical assembly) neutron spectrum averaged cross sections, and small-sized LANL fast system criticalities. The changes in the obtained evaluated cross sections from those in the JENDL-4.0 library are within 4% (<sup>241</sup>Pu), 3% (<sup>233</sup>U, <sup>240</sup>Pu), or 2% (<sup>235</sup>U, <sup>239</sup>Pu). The newly evaluated <sup>235</sup>U, <sup>238</sup>U and <sup>239</sup>Pu cross sections agree with the IAEA Neutron Data Standards 2017 within 2% with some exceptions.
DOI: 10.6084/m9.figshare.19692034.v2
title: EXFOR-based simultaneous evaluation of neutron-induced uranium and plutonium fission cross sections for JENDL-5

description: The neutron-induced fission cross sections were simultaneously evaluated for the JENDL-5 library for <sup>233,235</sup>U and <sup>239,241</sup>Pu from 10 keV to 200 MeV and for <sup>238</sup>U and <sup>240</sup>Pu from 100 keV to 200 MeV. Evaluation was performed by least-squares fitting of Schmittroth’s roof function to the logarithms of the experimental cross sections and cross section ratios in the EXFOR library. A simultaneous evaluation code SOK was used with its extension to data in arbitrary unit. The outputs of the code were adopted as the evaluated cross sections without any further corrections. The newly obtained evaluated cross sections were compared with the evaluated cross sections in the JENDL-4.0 library and the IAEA Neutron Data Standards 2017. The evaluated cross sections were also validated against the californium-252 spontaneous fission neutron spectrum averaged cross sections, ΣΣ (coupled thermal/fast uranium and boron carbide spherical assembly) neutron spectrum averaged cross sections, and small-sized LANL fast system criticalities. The changes in the obtained evaluated cross sections from those in the JENDL-4.0 library are within 4% (<sup>241</sup>Pu), 3% (<sup>233</sup>U, <sup>240</sup>Pu), or 2% (<sup>235</sup>U, <sup>239</sup>Pu). The newly evaluated <sup>235</sup>U, <sup>238</sup>U and <sup>239</sup>Pu cross sections agree with the IAEA Neutron Data Standards 2017 within 2% with some exceptions.
DOI: 10.15468/dl.9wxhb3
title: Occurrence Download

description: A dataset containing 194 species occurrences available in GBIF matching the query:
{
 "and" : [
 "Country is one of (India, Bangladesh, Myanmar, Nepal)",
 "TaxonKey is Argyreia nervosa (Burm.fil.) Bojer"
 ]
}

 The dataset includes 194 records from 22 constituent datasets; see https://api.gbif.org/v1/occurrence/download/0003187-250214102907787/datasets/export for details.
 
Data from some individual datasets included in this download may be licensed under less restrictive terms.
DOI: 10.5281/zenodo.13836947
title: Quantitative Assessment of Research Data Management Practices - 2023
title: Évaluation quantitative des pratiques de gestion des données de recherche - 2023
title: Valutazione quantitativa delle pratiche di gestione dei dati di ricerca - 2023
title: Quantitative Bewertung der Praktiken des Forschungsdatenmanagements - 2023

description: This survey investigates Research Data Management (RDM) practices across five Swiss higher education institutions, including EPFL, ETH Zürich, Eawag, FHNW, and DaSCH, with the goal of gathering insights into how researchers manage data and code throughout the lifecycle of their projects, as well as using such findings to inform academic services related to RDM for researchers. Previous surveys, conducted at EPFL in 2017, 2019, and 2021, primarily focused on the planning and publishing stages of the research data lifecycle, such as data management planning and open data dissemination. The 2023 edition expanded to other institutes and places a stronger emphasis on Active Data Management, particularly during research projects, including a range of topics such as:



Storage and backup solutions

Data and code sharing platforms

Documentation and metadata usage

Compliance with legal and ethical standards

Long-term data preservation strategies

Use of open formats and open-source software

Adoption of Data Management Plans (DMPs)


This dataset was collected using the SurveyHero platform in compliance with GDPR and Swiss FADP regulations. enuvo GmbH acted as the data processor under a signed Data Processing Agreement. No personal identifiable information was purposefully collected, and data has been aggregated to further ensure respondents’ privacy.

Included in this dataset:



A CSV and XLSX file with the aggregated, anonymized data from the survey.

Two PDF files containing graphical representations of the survey results, automatically generated by the SurveyHero platform in portrait and landscape mode.

A README file providing context.


This dataset is made openly available under the CC-BY 4.0 license. Users are encouraged to reuse it with appropriate attribution.
DOI: 10.5281/zenodo.13836948
title: Quantitative Assessment of Research Data Management Practices - 2023
title: Évaluation quantitative des pratiques de gestion des données de recherche - 2023
title: Valutazione quantitativa delle pratiche di gestione dei dati di ricerca - 2023
title: Quantitative Bewertung der Praktiken des Forschungsdatenmanagements - 2023

description: This survey investigates Research Data Management (RDM) practices across five Swiss higher education institutions, including EPFL, ETH Zürich, Eawag, FHNW, and DaSCH, with the goal of gathering insights into how researchers manage data and code throughout the lifecycle of their projects, as well as using such findings to inform academic services related to RDM for researchers. Previous surveys, conducted at EPFL in 2017, 2019, and 2021, primarily focused on the planning and publishing stages of the research data lifecycle, such as data management planning and open data dissemination. The 2023 edition expanded to other institutes and places a stronger emphasis on Active Data Management, particularly during research projects, including a range of topics such as:



Storage and backup solutions

Data and code sharing platforms

Documentation and metadata usage

Compliance with legal and ethical standards

Long-term data preservation strategies

Use of open formats and open-source software

Adoption of Data Management Plans (DMPs)


This dataset was collected using the SurveyHero platform in compliance with GDPR and Swiss FADP regulations. enuvo GmbH acted as the data processor under a signed Data Processing Agreement. No personal identifiable information was purposefully collected, and data has been aggregated to further ensure respondents’ privacy.

Included in this dataset:



A CSV and XLSX file with the aggregated, anonymized data from the survey.

Two PDF files containing graphical representations of the survey results, automatically generated by the SurveyHero platform in portrait and landscape mode.

A README file providing context.


This dataset is made openly available under the CC-BY 4.0 license. Users are encouraged to reuse it with appropriate attribution.
DOI: 10.6084/m9.figshare.17054856
title: Variation of Internal Doses Caused by Differences in Physical Characteristics between the Average Japanese and the ICRP’s Reference Man Which Is Based on the Standard Data of Caucasians in the Dosimetric Methodology in Conformity to the 2007 Recommendations

description: This paper describes a systematic analysis of the variation of internal doses derived from differences in physical characteristics in a dosimetric methodology fully based on the 2007 Recommendations of the International Commission on Radiological Protection (ICRP), including biokinetic models revised recently. Effective dose coefficients were estimated for the intakes of radionuclides reflecting the average physical characteristics of the adult Japanese, and compared with those provided by the ICRP, which have been evaluated using the physical constitution of the standard adult Caucasian (ICRP reference phantoms). Japanese dose coefficients were calculated using a dataset of specific absorbed fractions for the average adult Japanese, which was prepared by modification of the existing data with additional radiation transport calculations, combined with the current nuclear decay data and biokinetic models of ICRP. Comparison was made on 1339 conditions of intakes for 284 nuclides, which showed discrepancies in dose coefficients ranging from −37% to 44%. However, the discrepancies were smaller than 10% in 78% of all conditions. The extent of the variation in the dose coefficients will be acceptable for using the ICRP’s dose coefficients for the purpose of radiation protection for the Japanese.
DOI: 10.6084/m9.figshare.17054856.v2
title: Variation of Internal Doses Caused by Differences in Physical Characteristics between the Average Japanese and the ICRP’s Reference Man Which Is Based on the Standard Data of Caucasians in the Dosimetric Methodology in Conformity to the 2007 Recommendations

description: This paper describes a systematic analysis of the variation of internal doses derived from differences in physical characteristics in a dosimetric methodology fully based on the 2007 Recommendations of the International Commission on Radiological Protection (ICRP), including biokinetic models revised recently. Effective dose coefficients were estimated for the intakes of radionuclides reflecting the average physical characteristics of the adult Japanese, and compared with those provided by the ICRP, which have been evaluated using the physical constitution of the standard adult Caucasian (ICRP reference phantoms). Japanese dose coefficients were calculated using a dataset of specific absorbed fractions for the average adult Japanese, which was prepared by modification of the existing data with additional radiation transport calculations, combined with the current nuclear decay data and biokinetic models of ICRP. Comparison was made on 1339 conditions of intakes for 284 nuclides, which showed discrepancies in dose coefficients ranging from −37% to 44%. However, the discrepancies were smaller than 10% in 78% of all conditions. The extent of the variation in the dose coefficients will be acceptable for using the ICRP’s dose coefficients for the purpose of radiation protection for the Japanese.
DOI: 10.6084/m9.figshare.17054856.v1
title: Variation of Internal Doses Caused by Differences in Physical Characteristics between the Average Japanese and the ICRP’s Reference Man Which Is Based on the Standard Data of Caucasians in the Dosimetric Methodology in Conformity to the 2007 Recommendations

description: This paper describes a systematic analysis of the variation of internal doses derived from differences in physical characteristics in a dosimetric methodology fully based on the 2007 Recommendations of the International Commission on Radiological Protection (ICRP), including biokinetic models revised recently. Effective dose coefficients were estimated for the intakes of radionuclides reflecting the average physical characteristics of the adult Japanese, and compared with those provided by the ICRP, which have been evaluated using the physical constitution of the standard adult Caucasian (ICRP reference phantoms). Japanese dose coefficients were calculated using a dataset of specific absorbed fractions for the average adult Japanese, which was prepared by modification of the existing data with additional radiation transport calculations, combined with the current nuclear decay data and biokinetic models of ICRP. Comparison was made on 1339 conditions of intakes for 284 nuclides, which showed discrepancies in dose coefficients ranging from −37% to 44%. However, the discrepancies were smaller than 10% in 78% of all conditions. The extent of the variation in the dose coefficients will be acceptable for using the ICRP’s dose coefficients for the purpose of radiation protection for the Japanese.
DOI: 10.15468/dl.9xjd99
title: Occurrence Download

description: A dataset containing 1290 species occurrences available in GBIF matching the query:
{
 "TaxonKey" : [
 "is Pinna rudis Linnaeus, 1758"
 ]
}

 The dataset includes 1290 records from 70 constituent datasets; see https://api.gbif.org/v1/occurrence/download/0003188-250214102907787/datasets/export for details.
 
Data from some individual datasets included in this download may be licensed under less restrictive terms.
DOI: 10.5281/zenodo.12684826
title: Model Inputs and Results - The role of coal plant retrofitting strategies in decarbonizing India's power system

description: These files are the model inputs and results for the submission based on GenX version v0.3.6 - The role of coal plant retrofitting strategies in decarbonizing India’s power system
DOI: 10.5281/zenodo.12684827
title: Model Inputs and Results - The role of coal plant retrofitting strategies in decarbonizing India's power system

description: These files are the model inputs and results for the submission based on GenX version v0.3.6 - The role of coal plant retrofitting strategies in decarbonizing India’s power system
DOI: 10.5281/zenodo.14883716
title: Model Inputs and Results - The role of coal plant retrofitting strategies in decarbonizing India's power system

description: These files are the model inputs and results for the submission based on GenX version v0.3.6 - The role of coal plant retrofitting strategies in decarbonizing India’s power system
DOI: 10.25625/3txr94/16hdhq
title: GTP_MT_C36M_RUN_2_fragment.al

description: :unav
DOI: 10.25625/3txr94/1sbguq
title: GTP_MT_C36M_RUN_2.pdb

description: :unav
DOI: 10.25625/3txr94/3zf2y5
title: GTP_MT_C36M_RUN_1_fragment.ah

description: :unav
DOI: 10.25625/3txr94/4uu4pz
title: GTP_MT_C36M_RUN_1_fragment.aa

description: :unav
DOI: 10.25625/3txr94/8pw5fv
title: GTP_MT_C36M_RUN_3_fragment.aa

description: :unav
DOI: 10.25625/3txr94/a76jec
title: GTP_MT_C36M_RUN_2_fragment.am

description: :unav
DOI: 10.25625/3txr94/ae0c0s
title: GTP_MT_C36M_RUN_2_fragment.ai

description: :unav
DOI: 10.25625/3txr94/bgpq7x
title: GTP_MT_C36M_RUN_4_fragment.al

description: :unav
DOI: 10.25625/3txr94/bmh54v
title: GTP_MT_C36M_RUN_4_fragment.ai

description: :unav
DOI: 10.25625/3txr94/bunati
title: GTP_MT_C36M_RUN_2_fragment.ah

description: :unav
DOI: 10.25625/3txr94/c9cpmd
title: GTP_MT_C36M_RUN_1_fragment.ak

description: :unav
DOI: 10.25625/3txr94/dd63c3
title: GTP_MT_C36M_RUN_1.pdb

description: :unav
DOI: 10.25625/3txr94/dguwui
title: GTP_MT_C36M_RUN_3_fragment.af

description: :unav
DOI: 10.25625/3txr94/e9bwjw
title: GTP_MT_C36M_RUN_3.pdb

description: :unav
DOI: 10.25625/3txr94/ecamyl
title: GTP_MT_C36M_RUN_3_fragment.ah

description: :unav
DOI: 10.25625/3txr94/fzn4z7
title: GTP_MT_C36M_RUN_1_fragment.al

description: :unav
DOI: 10.25625/3txr94/ham66c
title: GTP_MT_C36M_RUN_3_fragment.am

description: :unav
DOI: 10.25625/3txr94/hauth7
title: GTP_MT_C36M_RUN_1_fragment.ai

description: :unav
DOI: 10.25625/3txr94/iqrkxl
title: GTP_MT_C36M_RUN_2_fragment.ab

description: :unav
DOI: 10.25625/3txr94/j3qzjf
title: GTP_MT_C36M_RUN_1_fragment.af

description: :unav
DOI: 10.25625/3txr94/ksyjb9
title: GTP_MT_C36M_RUN_4.pdb

description: :unav
DOI: 10.25625/3txr94/mff7sh
title: GTP_MT_C36M_RUN_1_fragment.ap

description: :unav
DOI: 10.25625/3txr94/nwp8l1
title: GTP_MT_C36M_RUN_2_fragment.af

description: :unav
DOI: 10.25625/3txr94/oeymv9
title: GTP_MT_C36M_RUN_3_fragment.ad

description: :unav
DOI: 10.25625/3txr94/ome10t
title: GTP_MT_C36M_RUN_1_fragment.an

description: :unav
DOI: 10.25625/3txr94/owkv6u
title: GTP_MT_C36M_RUN_2_fragment.ad

description: :unav
DOI: 10.25625/3txr94/ptuv2h
title: GTP_MT_C36M_RUN_1_fragment.am

description: :unav
DOI: 10.25625/3txr94/pwmdsj
title: GTP_MT_C36M_RUN_2_fragment.ag

description: :unav
DOI: 10.25625/3txr94/qbubyg
title: GTP_MT_C36M_RUN_1_fragment.aj

description: :unav
DOI: 10.25625/3txr94/r672i4
title: GTP_MT_C36M_RUN_3_fragment.ak

description: :unav
DOI: 10.25625/3txr94/rdf4vn
title: GTP_MT_C36M_RUN_3_fragment.ai

description: :unav
DOI: 10.25625/3txr94/rkrdst
title: GTP_MT_C36M_RUN_1_fragment.ag

description: :unav
DOI: 10.25625/3txr94/rl6ogr
title: GTP_MT_C36M_RUN_2_fragment.an

description: :unav
DOI: 10.25625/3txr94/wovwvn
title: GTP_MT_C36M_RUN_2_fragment.ae

description: :unav
DOI: 10.25625/3txr94/wsslxa
title: GTP_MT_C36M_RUN_1_fragment.ao

description: :unav
DOI: 10.25625/3txr94/xic8nj
title: GTP_MT_C36M_RUN_1_fragment.ae

description: :unav
DOI: 10.25625/3txr94/xkdd18
title: GTP_MT_C36M_RUN_1_fragment.ac

description: :unav
DOI: 10.25625/3txr94/xoargd
title: GTP_MT_C36M_RUN_1_fragment.ad

description: :unav
DOI: 10.25625/3txr94/yqtdsn
title: GTP_MT_C36M_RUN_1_fragment.ab

description: :unav
DOI: 10.25625/3txr94/8ixzr2
title: GTP_MT_C36M_RUN_5_fragment.ah

description: :unav
DOI: 10.25625/3txr94/aid7nd
title: GTP_MT_C36M_RUN_5_fragment.aa

description: :unav
DOI: 10.25625/3txr94/aqw04x
title: GTP_MT_C36M_RUN_2_fragment.aa

description: :unav
DOI: 10.25625/3txr94/bx64u5
title: GTP_MT_C36M_RUN_3_fragment.ae

description: :unav
DOI: 10.25625/3txr94/fgaq5x
title: GTP_MT_C36M_RUN_4_fragment.ae

description: :unav
DOI: 10.25625/3txr94/fiylxe
title: GTP_MT_C36M_RUN_3_fragment.ac

description: :unav
DOI: 10.25625/3txr94/giwvhy
title: GTP_MT_C36M_RUN_2_fragment.ac

description: :unav
DOI: 10.25625/3txr94/jieb8z
title: GTP_MT_C36M_RUN_4_fragment.am

description: :unav
DOI: 10.25625/3txr94/k05n0s
title: GTP_MT_C36M_RUN_5_fragment.ad

description: :unav
DOI: 10.25625/3txr94/k6xi9b
title: GTP_MT_C36M_RUN_4_fragment.ad

description: :unav
DOI: 10.25625/3txr94/koljfl
title: GTP_MT_C36M_RUN_3_fragment.aj

description: :unav
DOI: 10.25625/3txr94/kopguc
title: GTP_MT_C36M_RUN_5_fragment.af

description: :unav
DOI: 10.25625/3txr94/kqzl9g
title: GTP_MT_C36M_RUN_5_fragment.ac

description: :unav
DOI: 10.25625/3txr94/mmuwem
title: GTP_MT_C36M_RUN_5_fragment.ai

description: :unav
DOI: 10.25625/3txr94/po2ck4
title: GTP_MT_C36M_RUN_4_fragment.ac

description: :unav
DOI: 10.25625/3txr94/poahxj
title: GTP_MT_C36M_RUN_4_fragment.aj

description: :unav
DOI: 10.25625/3txr94/qf029i
title: GTP_MT_C36M_RUN_5_fragment.am

description: :unav
DOI: 10.25625/3txr94/qhnm19
title: GTP_MT_C36M_RUN_2_fragment.aj

description: :unav
DOI: 10.25625/3txr94/rmf8u9
title: GTP_MT_C36M_RUN_5_fragment.ag

description: :unav
DOI: 10.25625/3txr94/sasyof
title: GTP_MT_C36M_RUN_5_fragment.ao

description: :unav
DOI: 10.25625/3txr94/sjbsjv
title: GTP_MT_C36M_RUN_5_fragment.al

description: :unav
DOI: 10.25625/3txr94/sqindu
title: GTP_MT_C36M_RUN_5_fragment.ak

description: :unav
DOI: 10.25625/3txr94/t4lwzj
title: GTP_MT_C36M_RUN_5_fragment.an

description: :unav
DOI: 10.25625/3txr94/thef0l
title: GTP_MT_C36M_RUN_2_fragment.ak

description: :unav
DOI: 10.25625/3txr94/umkgjf
title: GTP_MT_C36M_RUN_4_fragment.ab

description: :unav