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@ARTICLE{Kuijper:57553,
      author       = {Kuijper, J. C. and Raepsaet, X. and de Haas, J. B. M. and
                      Von Lensa, W. and Ohlig, U. and Rütten, H.-J. and
                      Brockmann, H. and Damian, F. and Dolci, F. and Bernnat, W.
                      and Oppe, J. and Kloosterman, J. L. and Cerullo, N. and
                      Lomonaco, G. and Negrini, A. and Magill, J. and Seiler, R.},
      title        = {{HTGR} reactor physics and fuel cycle studies},
      journal      = {Nuclear engineering and design},
      volume       = {236},
      issn         = {0029-5493},
      address      = {Amsterdam [u.a.]},
      publisher    = {Elsevier Science},
      reportid     = {PreJuSER-57553},
      year         = {2006},
      note         = {Record converted from VDB: 12.11.2012},
      abstract     = {The high-temperature gas-cooled reactor (HTGR) appears as a
                      good candidate for the next generation of nuclear power
                      plants. In the "HTR-N" project of the European Union Fifth
                      Framework Program, analyses have been performed on a number
                      of conceptual HTGR designs, derived from reference
                      pebble-bed and hexagonal block-type HTGR types. It is shown
                      that several HTGR concepts are quite promising as systems
                      for the incineration of plutonium and possibly minor
                      actinides.These studies were mainly concerned with the
                      investigation and intercomparison of the plutonium and
                      actinide burning capabilities of a number of HTGR concepts
                      and associated fuel cycles, with emphasis on the use of
                      civil plutonium from spent LWR uranium fuel (first
                      generation Pu) and from spent LWR MOX fuel (second
                      generation Pu). Besides, the "HTR-N" project also included
                      activities concerning the validation of computational tools
                      and the qualification of models. Indeed, it is essential
                      that validated analytical tools are available in the
                      European nuclear community to perform conceptual design
                      studies, industrial calculations (reload calculations and
                      the associated core follow), safety analyses for licensing,
                      etc., for new fuel cycles aiming at plutonium and minor
                      actinide (MA) incineration/transinutation without
                      multi-reprocessing of the discharged fuel.These validation
                      and qualification activities have been centred round the two
                      HTGR systems currently in operation, viz. the HTR-10 and the
                      HTTR. The re-calculation of the HTTR first criticality with
                      a Monte Carlo neutron transport code now yields acceptable
                      correspondence with experimental data. Also calculations by
                      3D diffusion theory codes yield acceptable results. Special
                      attention, however, has to be given to the modelling of
                      neutron streaming effects. For the HTR-10 the analyses
                      focused on first criticality, temperature coefficients and
                      control rod worth. Also in these studies a good
                      correspondence between calculation and experiment is
                      observed for the 3D diffusion theory codes. (c) 2006
                      Elsevier B.V. All rights reserved.},
      keywords     = {J (WoSType)},
      cin          = {ISR},
      ddc          = {620},
      cid          = {I:(DE-Juel1)VDB182},
      pnm          = {Nukleare Sicherheitsforschung},
      pid          = {G:(DE-Juel1)FUEK404},
      shelfmark    = {Nuclear Science $\&$ Technology},
      typ          = {PUB:(DE-HGF)16},
      UT           = {WOS:000236894500019},
      doi          = {10.1016/j.nucengdes.2005.10.021},
      url          = {https://juser.fz-juelich.de/record/57553},
}