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| Home > Publications database > Benchmarking of MCNP for Calculating Dose Rates at an Interim Storage Facility for Nuclear Waste > print |
| 001 | 52131 | ||
| 005 | 20160504200911.0 | ||
| 024 | 7 | _ | |2 pmid |a pmid:16381760 |
| 024 | 7 | _ | |2 DOI |a 10.1093/rpd/nci185 |
| 024 | 7 | _ | |2 WOS |a WOS:000235218600087 |
| 037 | _ | _ | |a PreJuSER-52131 |
| 041 | _ | _ | |a eng |
| 082 | _ | _ | |a 333.7 |
| 084 | _ | _ | |2 WoS |a Environmental Sciences |
| 084 | _ | _ | |2 WoS |a Public, Environmental & Occupational Health |
| 084 | _ | _ | |2 WoS |a Nuclear Science & Technology |
| 084 | _ | _ | |2 WoS |a Radiology, Nuclear Medicine & Medical Imaging |
| 100 | 1 | _ | |a Heuel-Fabianek, B. |b 0 |u FZJ |0 P:(DE-Juel1)133423 |
| 245 | _ | _ | |a Benchmarking of MCNP for Calculating Dose Rates at an Interim Storage Facility for Nuclear Waste |
| 260 | _ | _ | |a Ashford |b Oxford Univ. Press |c 2005 |
| 300 | _ | _ | |a |
| 336 | 7 | _ | |a Journal Article |0 PUB:(DE-HGF)16 |2 PUB:(DE-HGF) |
| 336 | 7 | _ | |a Output Types/Journal article |2 DataCite |
| 336 | 7 | _ | |a Journal Article |0 0 |2 EndNote |
| 336 | 7 | _ | |a ARTICLE |2 BibTeX |
| 336 | 7 | _ | |a JOURNAL_ARTICLE |2 ORCID |
| 336 | 7 | _ | |a article |2 DRIVER |
| 440 | _ | 0 | |a Radiation Protection Dosimetry |x 0144-8420 |0 8244 |y 1 |v 115 |
| 500 | _ | _ | |a Record converted from VDB: 12.11.2012 |
| 520 | _ | _ | |a During 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. |
| 536 | _ | _ | |a Nukleare Sicherheitsforschung |c E04 |2 G:(DE-HGF) |0 G:(DE-Juel1)FUEK249 |x 0 |
| 588 | _ | _ | |a Dataset connected to Web of Science, Pubmed |
| 650 | _ | 2 | |2 MeSH |a Benchmarking |
| 650 | _ | 2 | |2 MeSH |a Computer Simulation |
| 650 | _ | 2 | |2 MeSH |a Germany |
| 650 | _ | 2 | |2 MeSH |a Models, Statistical |
| 650 | _ | 2 | |2 MeSH |a Monte Carlo Method |
| 650 | _ | 2 | |2 MeSH |a Radiation Dosage |
| 650 | _ | 2 | |2 MeSH |a Radiation Monitoring: methods |
| 650 | _ | 2 | |2 MeSH |a Radiation Monitoring: standards |
| 650 | _ | 2 | |2 MeSH |a Radiation Protection: instrumentation |
| 650 | _ | 2 | |2 MeSH |a Radiation Protection: methods |
| 650 | _ | 2 | |2 MeSH |a Radiation Protection: standards |
| 650 | _ | 2 | |2 MeSH |a Radioactive Waste: analysis |
| 650 | _ | 2 | |2 MeSH |a Radioisotopes: analysis |
| 650 | _ | 2 | |2 MeSH |a Refuse Disposal: instrumentation |
| 650 | _ | 2 | |2 MeSH |a Refuse Disposal: methods |
| 650 | _ | 2 | |2 MeSH |a Refuse Disposal: standards |
| 650 | _ | 2 | |2 MeSH |a Software |
| 650 | _ | 2 | |2 MeSH |a Software Validation |
| 650 | _ | 7 | |0 0 |2 NLM Chemicals |a Radioactive Waste |
| 650 | _ | 7 | |0 0 |2 NLM Chemicals |a Radioisotopes |
| 650 | _ | 7 | |a J |2 WoSType |
| 700 | 1 | _ | |a Hille, R. |b 1 |u FZJ |0 P:(DE-Juel1)VDB620 |
| 773 | _ | _ | |a 10.1093/rpd/nci185 |g Vol. 115 |q 115 |0 PERI:(DE-600)2121843-2 |t Radiation protection dosimetry |v 115 |y 2005 |x 0144-8420 |
| 856 | 7 | _ | |u http://dx.doi.org/10.1093/rpd/nci185 |
| 909 | C | O | |o oai:juser.fz-juelich.de:52131 |p VDB |
| 913 | 1 | _ | |k E04 |v Nukleare Sicherheitsforschung |l Nukleare Sicherheitsforschung |b Energie |0 G:(DE-Juel1)FUEK249 |x 0 |
| 914 | 1 | _ | |a Nachtrag |y 2005 |
| 915 | _ | _ | |0 StatID:(DE-HGF)0010 |a JCR/ISI refereed |
| 920 | 1 | _ | |k S |l Abteilung Sicherheit und Strahlenschutz |g S |0 I:(DE-Juel1)VDB224 |x 0 |
| 970 | _ | _ | |a VDB:(DE-Juel1)81885 |
| 980 | _ | _ | |a VDB |
| 980 | _ | _ | |a ConvertedRecord |
| 980 | _ | _ | |a journal |
| 980 | _ | _ | |a I:(DE-Juel1)VDB224 |
| 980 | _ | _ | |a UNRESTRICTED |
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