From f3da500baf2db7a647e24ab3575d27c7a7234d05 Mon Sep 17 00:00:00 2001 From: CNERG Zotero Bot Date: Thu, 5 Sep 2024 00:58:11 +0000 Subject: [PATCH] Updating the publication data from Zotero --- _data/pub.json | 11 +++++++---- _data/zotero.datestamp | 2 +- 2 files changed, 8 insertions(+), 5 deletions(-) diff --git a/_data/pub.json b/_data/pub.json index 4cd782ec..0609bf0f 100644 --- a/_data/pub.json +++ b/_data/pub.json @@ -808,7 +808,7 @@ }, { "key": "7EJ4AFK3", - "version": 27454, + "version": 30599, "library": { "type": "group", "id": 10058, @@ -852,10 +852,10 @@ "parsedDate": "2023-01-02", "numChildren": 1 }, - "bibtex": "\n@article{harb_uncertainty_2023,\n\ttitle = {Uncertainty {Quantification} of the {Decay} {Gamma} {Source} in {Mesh}-{Based} {Shutdown} {Dose} {Rate} {Calculations}},\n\tvolume = {79},\n\tissn = {1536-1055},\n\turl = {https://doi.org/10.1080/15361055.2022.2115831},\n\tdoi = {10.1080/15361055.2022.2115831},\n\tabstract = {In fusion energy systems, part of the design effort is dedicated to the assessment of the shutdown dose rate (SDR) due to the decay photons that will be emitted from activated components. Monte Carlo transport codes are often used to obtain the neutron flux distribution in the problem domain. The neutron flux distribution is used in the rigorous 2-step (R2S) workflow to obtain the photon emission density distribution of decaying radionuclides. The photon emission density is then used as an input for a dedicated photon transport step to calculate the SDR. In this paper, the uncertainty of the decay gamma source due to the uncertainty of the neutron flux distribution in the R2S workflow is investigated. A scheme is developed to estimate the uncertainty of the decay gamma source, building on the concept of groupwise transmutation and using standard error propagation techniques. The applicability of the newly developed scheme is then demonstrated on one of the conceptual designs of the fusion nuclear science facility.},\n\tnumber = {1},\n\turldate = {2022-12-14},\n\tjournal = {Fusion Science and Technology},\n\tauthor = {Harb, M. and Davis, A. and Wilson, P. P. H.},\n\tmonth = jan,\n\tyear = {2023},\n\tnote = {Publisher: Taylor \\& Francis\n\\_eprint: https://doi.org/10.1080/15361055.2022.2115831},\n\tkeywords = {DAGMC, Uncertainty propagation, fusion nuclear science facility, rigorous 2-step workflow, shutdown dose rate},\n\tpages = {1--12},\n}\n", + "bibtex": "\n@article{harb_uncertainty_2023,\n\ttitle = {Uncertainty {Quantification} of the {Decay} {Gamma} {Source} in {Mesh}-{Based} {Shutdown} {Dose} {Rate} {Calculations}},\n\tvolume = {79},\n\tissn = {1536-1055},\n\turl = {https://doi.org/10.1080/15361055.2022.2115831},\n\tdoi = {10.1080/15361055.2022.2115831},\n\tabstract = {In fusion energy systems, part of the design effort is dedicated to the assessment of the shutdown dose rate (SDR) due to the decay photons that will be emitted from activated components. Monte Carlo transport codes are often used to obtain the neutron flux distribution in the problem domain. The neutron flux distribution is used in the rigorous 2-step (R2S) workflow to obtain the photon emission density distribution of decaying radionuclides. The photon emission density is then used as an input for a dedicated photon transport step to calculate the SDR. In this paper, the uncertainty of the decay gamma source due to the uncertainty of the neutron flux distribution in the R2S workflow is investigated. A scheme is developed to estimate the uncertainty of the decay gamma source, building on the concept of groupwise transmutation and using standard error propagation techniques. The applicability of the newly developed scheme is then demonstrated on one of the conceptual designs of the fusion nuclear science facility.},\n\tnumber = {1},\n\turldate = {2022-12-14},\n\tjournal = {Fusion Science and Technology},\n\tauthor = {Harb, M. and Davis, A. and Wilson, P. P. H.},\n\tmonth = jan,\n\tyear = {2023},\n\tnote = {Publisher: Taylor \\& Francis\n\\_eprint: https://doi.org/10.1080/15361055.2022.2115831},\n\tkeywords = {DAGMC, FIRE MIT, Uncertainty propagation, fusion nuclear science facility, rigorous 2-step workflow, shutdown dose rate},\n\tpages = {1--12},\n}\n", "data": { "key": "7EJ4AFK3", - "version": 27454, + "version": 30599, "itemType": "journalArticle", "title": "Uncertainty Quantification of the Decay Gamma Source in Mesh-Based Shutdown Dose Rate Calculations", "creators": [ @@ -902,6 +902,9 @@ "tag": "DAGMC", "type": 1 }, + { + "tag": "FIRE MIT" + }, { "tag": "Uncertainty propagation", "type": 1 @@ -925,7 +928,7 @@ ], "relations": {}, "dateAdded": "2022-12-14T23:18:26Z", - "dateModified": "2022-12-14T23:18:26Z" + "dateModified": "2024-09-04T15:53:59Z" } }, { diff --git a/_data/zotero.datestamp b/_data/zotero.datestamp index 07d95a62..987afea7 100644 --- a/_data/zotero.datestamp +++ b/_data/zotero.datestamp @@ -1 +1 @@ -Sun Sep 1 06:04:25 UTC 2024 +Thu Sep 5 00:58:11 UTC 2024