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@ARTICLE{HeuelFabianek:52131,
      author       = {Heuel-Fabianek, B. and Hille, R.},
      title        = {{B}enchmarking of {MCNP} for {C}alculating {D}ose {R}ates
                      at an {I}nterim {S}torage {F}acility for {N}uclear {W}aste},
      journal      = {Radiation protection dosimetry},
      volume       = {115},
      issn         = {0144-8420},
      address      = {Ashford},
      publisher    = {Oxford Univ. Press},
      reportid     = {PreJuSER-52131},
      year         = {2005},
      note         = {Record converted from VDB: 12.11.2012},
      abstract     = {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.},
      keywords     = {Benchmarking / Computer Simulation / Germany / Models,
                      Statistical / Monte Carlo Method / Radiation Dosage /
                      Radiation Monitoring: methods / Radiation Monitoring:
                      standards / Radiation Protection: instrumentation /
                      Radiation Protection: methods / Radiation Protection:
                      standards / Radioactive Waste: analysis / Radioisotopes:
                      analysis / Refuse Disposal: instrumentation / Refuse
                      Disposal: methods / Refuse Disposal: standards / Software /
                      Software Validation / Radioactive Waste (NLM Chemicals) /
                      Radioisotopes (NLM Chemicals) / J (WoSType)},
      cin          = {S},
      ddc          = {333.7},
      cid          = {I:(DE-Juel1)VDB224},
      pnm          = {Nukleare Sicherheitsforschung},
      pid          = {G:(DE-Juel1)FUEK249},
      shelfmark    = {Environmental Sciences / Public, Environmental $\&$
                      Occupational Health / Nuclear Science $\&$ Technology /
                      Radiology, Nuclear Medicine $\&$ Medical Imaging},
      typ          = {PUB:(DE-HGF)16},
      pubmed       = {pmid:16381760},
      UT           = {WOS:000235218600087},
      doi          = {10.1093/rpd/nci185},
      url          = {https://juser.fz-juelich.de/record/52131},
}