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000052131 0247_ $$2DOI$$a10.1093/rpd/nci185
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000052131 084__ $$2WoS$$aEnvironmental Sciences
000052131 084__ $$2WoS$$aPublic, Environmental & Occupational Health
000052131 084__ $$2WoS$$aNuclear Science & Technology
000052131 084__ $$2WoS$$aRadiology, Nuclear Medicine & Medical Imaging
000052131 1001_ $$0P:(DE-Juel1)133423$$aHeuel-Fabianek, B.$$b0$$uFZJ
000052131 245__ $$aBenchmarking of MCNP for Calculating Dose Rates at an Interim Storage Facility for Nuclear Waste
000052131 260__ $$aAshford$$bOxford Univ. Press$$c2005
000052131 300__ $$a
000052131 3367_ $$0PUB:(DE-HGF)16$$2PUB:(DE-HGF)$$aJournal Article
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000052131 440_0 $$08244$$aRadiation Protection Dosimetry$$v115$$x0144-8420$$y1
000052131 500__ $$aRecord converted from VDB: 12.11.2012
000052131 520__ $$aDuring the operation of research facilities at Research Centre Jülich, Germany, nuclear waste is stored in drums and other vessels in an interim storage building on-site, which has a concrete shielding at the side walls. Owing to the lack of a well-defined source, measured gamma spectra were unfolded to determine the photon flux on the surface of the containers. The dose rate simulation, including the effects of skyshine, using the Monte Carlo transport code MCNP is compared with the measured dosimetric data at some locations in the vicinity of the interim storage building. The MCNP data for direct radiation confirm the data calculated using a point-kernel method. However, a comparison of the modelled dose rates for direct radiation and skyshine with the measured data demonstrate the need for a more precise definition of the source. Both the measured and the modelled dose rates verified the fact that the legal limits (<1 mSv a(-1)) are met in the area outside the perimeter fence of the storage building to which members of the public have access. Using container surface data (gamma spectra) to define the source may be a useful tool for practical calculations and additionally for benchmarking of computer codes if the discussed critical aspects with respect to the source can be addressed adequately.
000052131 536__ $$0G:(DE-Juel1)FUEK249$$2G:(DE-HGF)$$aNukleare Sicherheitsforschung$$cE04$$x0
000052131 588__ $$aDataset connected to Web of Science, Pubmed
000052131 650_2 $$2MeSH$$aBenchmarking
000052131 650_2 $$2MeSH$$aComputer Simulation
000052131 650_2 $$2MeSH$$aGermany
000052131 650_2 $$2MeSH$$aModels, Statistical
000052131 650_2 $$2MeSH$$aMonte Carlo Method
000052131 650_2 $$2MeSH$$aRadiation Dosage
000052131 650_2 $$2MeSH$$aRadiation Monitoring: methods
000052131 650_2 $$2MeSH$$aRadiation Monitoring: standards
000052131 650_2 $$2MeSH$$aRadiation Protection: instrumentation
000052131 650_2 $$2MeSH$$aRadiation Protection: methods
000052131 650_2 $$2MeSH$$aRadiation Protection: standards
000052131 650_2 $$2MeSH$$aRadioactive Waste: analysis
000052131 650_2 $$2MeSH$$aRadioisotopes: analysis
000052131 650_2 $$2MeSH$$aRefuse Disposal: instrumentation
000052131 650_2 $$2MeSH$$aRefuse Disposal: methods
000052131 650_2 $$2MeSH$$aRefuse Disposal: standards
000052131 650_2 $$2MeSH$$aSoftware
000052131 650_2 $$2MeSH$$aSoftware Validation
000052131 650_7 $$00$$2NLM Chemicals$$aRadioactive Waste
000052131 650_7 $$00$$2NLM Chemicals$$aRadioisotopes
000052131 650_7 $$2WoSType$$aJ
000052131 7001_ $$0P:(DE-Juel1)VDB620$$aHille, R.$$b1$$uFZJ
000052131 773__ $$0PERI:(DE-600)2121843-2$$a10.1093/rpd/nci185$$gVol. 115$$q115$$tRadiation protection dosimetry$$v115$$x0144-8420$$y2005
000052131 8567_ $$uhttp://dx.doi.org/10.1093/rpd/nci185
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000052131 9141_ $$aNachtrag$$y2005
000052131 915__ $$0StatID:(DE-HGF)0010$$aJCR/ISI refereed
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