Overview of straight duct streaming experiments for ITER
Two straight duct streaming experiments for international thermonuclear experimental reactor (ITER) were performed by using the intense deuterium–tritium (D–T) neutron source at Japan Atomic Energy Research Institute (JAERI) in order to investigate the influence of streaming through ducts on radiati...
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Veröffentlicht in: | Fusion engineering and design 2000-11, Vol.51, p.797-802 |
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creator | Konno, Chikara Maekawa, Fujio Uno, Yoshitomo Kasugai, Yoshimi Wada, Masayuki Ikeda, Yujiro Takeuchi, Hiroshi |
description | Two straight duct streaming experiments for international thermonuclear experimental reactor (ITER) were performed by using the intense deuterium–tritium (D–T) neutron source at Japan Atomic Energy Research Institute (JAERI) in order to investigate the influence of streaming through ducts on radiation dose and to validate the accuracy of design calculations. One was a small duct streaming experiment for diagnostic ports, the other was a large duct streaming experiment for large ports such as neutral beam injector (NBI) port. The ducts increased the neutron flux above 10 MeV by 10
6–10
7 times at the ends of the ducts, while the increase of neutron flux below 10 MeV and γ-ray by the ducts was less than a few hundred times. These experiments were analyzed by the MCNP-4A code with three nuclear data libraries: FENDL/E-2.0, -1.0 and JENDL Fusion File. Though the ducts made complicated neutron and γ-ray flux distributions in a cavity region, most of the calculated results agreed within ±40% with the experimental data. It was demonstrated that the MCNP calculations with the nuclear data libraries were accurate enough for predicting nuclear design parameters of ITER even for various duct geometries as far as they were modeled precisely. |
doi_str_mv | 10.1016/S0920-3796(00)00185-X |
format | Article |
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6–10
7 times at the ends of the ducts, while the increase of neutron flux below 10 MeV and γ-ray by the ducts was less than a few hundred times. These experiments were analyzed by the MCNP-4A code with three nuclear data libraries: FENDL/E-2.0, -1.0 and JENDL Fusion File. Though the ducts made complicated neutron and γ-ray flux distributions in a cavity region, most of the calculated results agreed within ±40% with the experimental data. It was demonstrated that the MCNP calculations with the nuclear data libraries were accurate enough for predicting nuclear design parameters of ITER even for various duct geometries as far as they were modeled precisely.</description><identifier>ISSN: 0920-3796</identifier><identifier>EISSN: 1873-7196</identifier><identifier>DOI: 10.1016/S0920-3796(00)00185-X</identifier><identifier>CODEN: FEDEEE</identifier><language>eng</language><publisher>Amsterdam: Elsevier B.V</publisher><subject>Applied sciences ; Controled nuclear fusion plants ; Design ; Deuterium ; Dosimetry ; Duct ; Energy ; Energy. Thermal use of fuels ; Exact sciences and technology ; Experimental reactors ; Gamma rays ; Installations for energy generation and conversion: thermal and electrical energy ; Neutron ; Neutron sources ; Tritium</subject><ispartof>Fusion engineering and design, 2000-11, Vol.51, p.797-802</ispartof><rights>2000 Elsevier Science B.V.</rights><rights>2001 INIST-CNRS</rights><lds50>peer_reviewed</lds50><woscitedreferencessubscribed>false</woscitedreferencessubscribed><citedby>FETCH-LOGICAL-c367t-e88f34338a1d47df577e35680d58d5d7cc1f08b84b937dd1fadbd3f2dabe0b9a3</citedby><cites>FETCH-LOGICAL-c367t-e88f34338a1d47df577e35680d58d5d7cc1f08b84b937dd1fadbd3f2dabe0b9a3</cites></display><links><openurl>$$Topenurl_article</openurl><openurlfulltext>$$Topenurlfull_article</openurlfulltext><thumbnail>$$Tsyndetics_thumb_exl</thumbnail><linktohtml>$$Uhttps://www.sciencedirect.com/science/article/pii/S092037960000185X$$EHTML$$P50$$Gelsevier$$H</linktohtml><link.rule.ids>309,310,314,776,780,785,786,3537,23909,23910,25118,27901,27902,65306</link.rule.ids><backlink>$$Uhttp://pascal-francis.inist.fr/vibad/index.php?action=getRecordDetail&idt=859678$$DView record in Pascal Francis$$Hfree_for_read</backlink></links><search><creatorcontrib>Konno, Chikara</creatorcontrib><creatorcontrib>Maekawa, Fujio</creatorcontrib><creatorcontrib>Uno, Yoshitomo</creatorcontrib><creatorcontrib>Kasugai, Yoshimi</creatorcontrib><creatorcontrib>Wada, Masayuki</creatorcontrib><creatorcontrib>Ikeda, Yujiro</creatorcontrib><creatorcontrib>Takeuchi, Hiroshi</creatorcontrib><title>Overview of straight duct streaming experiments for ITER</title><title>Fusion engineering and design</title><description>Two straight duct streaming experiments for international thermonuclear experimental reactor (ITER) were performed by using the intense deuterium–tritium (D–T) neutron source at Japan Atomic Energy Research Institute (JAERI) in order to investigate the influence of streaming through ducts on radiation dose and to validate the accuracy of design calculations. One was a small duct streaming experiment for diagnostic ports, the other was a large duct streaming experiment for large ports such as neutral beam injector (NBI) port. The ducts increased the neutron flux above 10 MeV by 10
6–10
7 times at the ends of the ducts, while the increase of neutron flux below 10 MeV and γ-ray by the ducts was less than a few hundred times. These experiments were analyzed by the MCNP-4A code with three nuclear data libraries: FENDL/E-2.0, -1.0 and JENDL Fusion File. Though the ducts made complicated neutron and γ-ray flux distributions in a cavity region, most of the calculated results agreed within ±40% with the experimental data. It was demonstrated that the MCNP calculations with the nuclear data libraries were accurate enough for predicting nuclear design parameters of ITER even for various duct geometries as far as they were modeled precisely.</description><subject>Applied sciences</subject><subject>Controled nuclear fusion plants</subject><subject>Design</subject><subject>Deuterium</subject><subject>Dosimetry</subject><subject>Duct</subject><subject>Energy</subject><subject>Energy. 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Thermal use of fuels</topic><topic>Exact sciences and technology</topic><topic>Experimental reactors</topic><topic>Gamma rays</topic><topic>Installations for energy generation and conversion: thermal and electrical energy</topic><topic>Neutron</topic><topic>Neutron sources</topic><topic>Tritium</topic><toplevel>peer_reviewed</toplevel><toplevel>online_resources</toplevel><creatorcontrib>Konno, Chikara</creatorcontrib><creatorcontrib>Maekawa, Fujio</creatorcontrib><creatorcontrib>Uno, Yoshitomo</creatorcontrib><creatorcontrib>Kasugai, Yoshimi</creatorcontrib><creatorcontrib>Wada, Masayuki</creatorcontrib><creatorcontrib>Ikeda, Yujiro</creatorcontrib><creatorcontrib>Takeuchi, Hiroshi</creatorcontrib><collection>Pascal-Francis</collection><collection>CrossRef</collection><collection>Mechanical Engineering Abstracts</collection><jtitle>Fusion engineering and design</jtitle></facets><delivery><delcategory>Remote Search Resource</delcategory><fulltext>fulltext</fulltext></delivery><addata><au>Konno, Chikara</au><au>Maekawa, Fujio</au><au>Uno, Yoshitomo</au><au>Kasugai, Yoshimi</au><au>Wada, Masayuki</au><au>Ikeda, Yujiro</au><au>Takeuchi, Hiroshi</au><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>Overview of straight duct streaming experiments for ITER</atitle><jtitle>Fusion engineering and design</jtitle><date>2000-11-01</date><risdate>2000</risdate><volume>51</volume><spage>797</spage><epage>802</epage><pages>797-802</pages><issn>0920-3796</issn><eissn>1873-7196</eissn><coden>FEDEEE</coden><abstract>Two straight duct streaming experiments for international thermonuclear experimental reactor (ITER) were performed by using the intense deuterium–tritium (D–T) neutron source at Japan Atomic Energy Research Institute (JAERI) in order to investigate the influence of streaming through ducts on radiation dose and to validate the accuracy of design calculations. One was a small duct streaming experiment for diagnostic ports, the other was a large duct streaming experiment for large ports such as neutral beam injector (NBI) port. The ducts increased the neutron flux above 10 MeV by 10
6–10
7 times at the ends of the ducts, while the increase of neutron flux below 10 MeV and γ-ray by the ducts was less than a few hundred times. These experiments were analyzed by the MCNP-4A code with three nuclear data libraries: FENDL/E-2.0, -1.0 and JENDL Fusion File. Though the ducts made complicated neutron and γ-ray flux distributions in a cavity region, most of the calculated results agreed within ±40% with the experimental data. It was demonstrated that the MCNP calculations with the nuclear data libraries were accurate enough for predicting nuclear design parameters of ITER even for various duct geometries as far as they were modeled precisely.</abstract><cop>Amsterdam</cop><cop>New York, NY</cop><pub>Elsevier B.V</pub><doi>10.1016/S0920-3796(00)00185-X</doi><tpages>6</tpages></addata></record> |
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subjects | Applied sciences Controled nuclear fusion plants Design Deuterium Dosimetry Duct Energy Energy. Thermal use of fuels Exact sciences and technology Experimental reactors Gamma rays Installations for energy generation and conversion: thermal and electrical energy Neutron Neutron sources Tritium |
title | Overview of straight duct streaming experiments for ITER |
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