{"status":"ok","message-type":"work","message-version":"1.0.0","message":{"indexed":{"date-parts":[[2026,9,18]],"date-time":"2026-09-18T14:01:55Z","timestamp":1789740115453,"version":"4.0.1"},"reference-count":25,"publisher":"Wiley","issue":"8","license":[{"start":{"date-parts":[[2026,7,30]],"date-time":"2026-07-30T00:00:00Z","timestamp":1785369600000},"content-version":"vor","delay-in-days":0,"URL":"http:\/\/creativecommons.org\/licenses\/by\/4.0\/"},{"start":{"date-parts":[[2026,7,30]],"date-time":"2026-07-30T00:00:00Z","timestamp":1785369600000},"content-version":"tdm","delay-in-days":0,"URL":"http:\/\/doi.wiley.com\/10.1002\/tdm_license_1.1"}],"content-domain":{"domain":["aapm.onlinelibrary.wiley.com"],"crossmark-restriction":true},"short-container-title":["J Applied Clin Med Phys"],"published-print":{"date-parts":[[2026,8]]},"abstract":"<jats:title>Abstract<\/jats:title>\n                  <jats:sec>\n                    <jats:title>Background<\/jats:title>\n                    <jats:p>\n                      Conventional radiotherapy vault shielding typically employs 2 to 3 meters of ordinary concrete, consistent with NCRP Report 151 reference data. While NCRP 151 specifies dose\u2010based design goals rather than mandating particular materials, the practical default of concrete results in vault footprints of 150 to 200\u00a0m\n                      <jats:sup>2<\/jats:sup>\n                      per linac, which can constrain treatment capacity within fixed departmental space. Recent advances in high\u2010density composite shielding materials offer the potential to achieve the same dose\u2010based design goals with reduced barrier thickness.\n                    <\/jats:p>\n                  <\/jats:sec>\n                  <jats:sec>\n                    <jats:title>Purpose<\/jats:title>\n                    <jats:p>In this study, we investigate advanced shielding materials, including specialty concretes and high\u2010density polymer composites, as potential alternatives to conventional concrete barriers, aiming to demonstrate that modern materials could safely enable more compact vault designs while maintaining regulatory compliance.<\/jats:p>\n                  <\/jats:sec>\n                  <jats:sec>\n                    <jats:title>Methods<\/jats:title>\n                    <jats:p>TOPAS Monte Carlo simulations evaluated a 6 MV and an 18\u00a0MV linear accelerator (LINAC) vault comparing conventional concrete against five candidate shielding materials. We modeled a typical 4\u2010vault radiotherapy department to demonstrate potential capacity increase. Simulations calculated linear attenuation coefficients (\u03bc), tenth\u2010value layers (TVLs), and dose distributions at regulatory measurement points. Spatial analyses projected the clinical impact of implementing optimized shielding.<\/jats:p>\n                  <\/jats:sec>\n                  <jats:sec>\n                    <jats:title>Results<\/jats:title>\n                    <jats:p>While concrete required 165.8 m2 floor area per vault, candidate materials achieved 17%\u201332% reductions for 6 MV beams and 22%\u201334% reductions for 18 MV beams. Specifically, Steel\u2010magnetite and Datolite\u2010Galena concretes showed great space\u2010saving potentials with footprint reductions of 28% and 31% for 18 MV beams, respectively, while maintaining refined doses at 2.40 \u00d7 10\u22122 and 2.42 \u00d7 10\u22122 mSv\/week, well below the 0.1 mSv\/week NCRP limit.<\/jats:p>\n                  <\/jats:sec>\n                  <jats:sec>\n                    <jats:title>Conclusion<\/jats:title>\n                    <jats:p>This study demonstrates that high\u2010density composite shielding may reduce vault footprint while maintaining dose levels below established shielding design limits. These findings suggest that systematic evaluation of alternative shielding materials may provide useful insights for space\u2010efficient radiotherapy vault design while remaining within established dose\u2010based shielding frameworks.<\/jats:p>\n                  <\/jats:sec>","DOI":"10.1002\/acm2.70728","type":"journal-article","created":{"date-parts":[[2026,7,31]],"date-time":"2026-07-31T06:54:12Z","timestamp":1785480852000},"update-policy":"https:\/\/doi.org\/10.1002\/crossmark_policy","source":"Crossref","is-referenced-by-count":0,"title":["Monte carlo assessment of advanced shielding materials for space\u2010efficient radiotherapy vault design"],"prefix":"10.1002","volume":"27","author":[{"given":"Beechui","family":"Koo","sequence":"first","affiliation":[{"name":"Data Science Institute University of Chicago  Chicago Illinois USA"},{"name":"Department of Radiation Medicine University of Wisconsin\u2010Madison  Medison Wisconsin USA"}],"role":[{"vocabulary":"crossref","role":"author"}]},{"given":"Richard","family":"Xu","sequence":"additional","affiliation":[{"name":"Department of Radiation Medicine University of Wisconsin\u2010Madison  Medison Wisconsin USA"}],"role":[{"vocabulary":"crossref","role":"author"}]},{"given":"Morgan","family":"Glennie","sequence":"additional","affiliation":[{"name":"Department of Radiation Medicine University of Wisconsin\u2010Madison  Medison Wisconsin USA"}],"role":[{"vocabulary":"crossref","role":"author"}]},{"given":"Jungwook","family":"Shin","sequence":"additional","affiliation":[{"name":"Division of Cancer Epidemiology and Genetics National Cancer Institute National Institutes of Health  Rockville Maryland USA"}],"role":[{"vocabulary":"crossref","role":"author"}]},{"given":"Karl","family":"Farrey","sequence":"additional","affiliation":[{"name":"Department of Radiation Medicine University of Wisconsin\u2010Madison  Medison Wisconsin USA"}],"role":[{"vocabulary":"crossref","role":"author"}]},{"given":"Siyong","family":"Kim","sequence":"additional","affiliation":[{"name":"Department of Radiation Oncology Virginia Commonwealth University  Richmond Virginia USA"}],"role":[{"vocabulary":"crossref","role":"author"}]},{"given":"James J.","family":"Sohn","sequence":"additional","affiliation":[{"name":"Department of Radiation Medicine University of Wisconsin\u2010Madison  Medison Wisconsin USA"}],"role":[{"vocabulary":"crossref","role":"author"}]}],"member":"311","published-online":{"date-parts":[[2026,7,30]]},"reference":[{"key":"e_1_2_10_2_1","unstructured":"NCRP Report No. 151.Structural shielding design and evaluation for megavoltage x\u2010 and gamma\u2010ray radiotherapy facilities.National Council on Radiation Protection and Measurements.2005."},{"key":"e_1_2_10_3_1","doi-asserted-by":"publisher","DOI":"10.1088\/0031-9155\/54\/5\/011"},{"key":"e_1_2_10_4_1","unstructured":"IAEA Safety Reports Series No. 47.Radiation protection in the design of radiotherapy facilities.International Atomic Energy Agency;2006."},{"issue":"9","key":"e_1_2_10_5_1","first-page":"1004","article-title":"Photoneutrons in high\u2010energy radiotherapy: sources, mitigation and shielding","volume":"79","author":"Naseri A","year":"2010","journal-title":"Radiat Phys Chem"},{"issue":"4","key":"e_1_2_10_6_1","first-page":"465","article-title":"Monte Carlo study on shielding properties of PVA\/WO3 nanocomposites against gamma rays","volume":"9","author":"Kazemi F","year":"2019","journal-title":"J Biomed Phys Eng"},{"issue":"1","key":"e_1_2_10_7_1","first-page":"11","article-title":"Production of datolite\u2013galena heavy concrete for shielding nuclear reactors and megavoltage radiotherapy rooms","volume":"8","author":"Mortazavi SMJ","year":"2010","journal-title":"Int J Radiat 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