JAEA図書館を検索します。
CiNii Booksを検索します。
CiNii Research(論文)を検索します。
IRDBを検索します。
PubMedを検索します。
NDLサーチを検索します。
機構内の蔵書を検索した結果です。電子媒体は詳細画面から外部へリンクする事が可能です。 ※なお、機構が購読する電子ジャーナル・電子ブックの本文の閲覧は原則として機構内からの利用となります。 機構職員等で、機構外からの電子ジャーナル等の利用について確認されたい方はこちら(機構内でのみ閲覧可能)をご確認ください。
検索キーワード:(著者名に左の語を含む: #PARKS C.V.)
該当件数:64件
Summary description of the scale modular code system
: Oak Ridge National Lab., TN (USA)(Oak Ridge National Lab., TN (USA)) , 1987. - (ORNL/CSD/TM ; ORNL/CSD/TM-252)
レポート
ASSESSMENT OF SHIELDING ANALYSIS METHODS, CODES, AND DATA FOR SPENT FUEL TRANSPORT/STORAGE APPLICATIONS. / PARKS, C.V.(et al.)
: Oak Ridge National Lab., Tenn. (USA)(Oak Ridge National Lab., Tenn. (USA)) , 1988. - (ORNL/CSD/TM ; ORNL/CSD/TM-246)
COMPUTATIONAL METHODS FOR CRITICALITY SAFETY ANALYSIS WITHIN THE SCALE SYSTEM. / PARKS, C.V.(et al.)
, 1986. - (CONF ; CONF-8606146-5)
PHENOMENA AND PARAMETERS IMPORTANT TO BURNUP CREDIT. / PARKS, C.V.
, 2001. - (P00 ; P00-109216)
DEVELOPMENT OF NUCLEAR ANALYSIS CAPABILITIES FOR DOE WASTE MANAGEMENT ACTIVITIES. / PARKS, C.V.(et al.)
: Oak Ridge National Laboratory(Oak Ridge National Laboratory) , 1998. - (ORNL ; ORNL/M-6549; DE98058119)
RADIATION DOSE RATES FROM CONSOLIDATED FUEL IN CURRENT GENERATION SHIPPING CASKS. / PARKS, C.V.(et al.)
, 1985. - (CONF ; CONF-851115-32)
REVIEW AND PRIORITIZATION OF TECHNICAL ISSUES RELATED TO BURNUP CREDIT FOR LWR FUEL (TECHNICAL REPT) / PARKS, C.V.(et al.)
: Oak Ridge National Laboratory(Oak Ridge National Laboratory) , 2000. - (ORNL ; ORNL/TM-1999/303; NUREG/CR-6665)
: Oak Ridge National Laboratory(Oak Ridge National Laboratory) , 1988. - (ORNL ; ORNL/CSD/TM-246)
ASSESSMENT OF THE US REGULATIONS FOR FISSILE EXEMPTIONS AND FISSILE MATERIAL GENERAL LICENSES. / PARKS, C.V.(et al.)
: Oak Ridge National Laboratory(Oak Ridge National Laboratory) , 1997. - (ORNL ; ORNL/CP-96994; DE98003373)
Overview of the SCALE-4 code system / Parks, C.V.
TN (USA) : Oak Ridge National Lab. , 1991.12.31. - (CONF ; CONF-9109217-6; DE92005474)
PARAMETRIC STUDY OF RADIATION DOSE RATES FROM RAIL AND TRUCK SPENT FUEL TRANSPORT CASKS. / PARKS, C.V.(et al.)
: Oak Ridge National Laboratory(Oak Ridge National Laboratory) , 1985. - (ORNL ; ORNL/CSD/TM-227)
SUMMARY DESCRIPTION OF THE SCALE MODULAR CODE SYSTEM. / PARKS, C.V.
: NUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission)) , 1987. - (NUREG ; NUREG/CR-5033)
RESEARCH SUPPORTING IMPLEMENTATION OF BURNUP CREDIT IN THE CRITICALITY SAFETY ASSESSMENT OF TRANSPORT AND STORAGE CASKS. / PARKS, C.V.
, 2001. - (P00 ; P00-109095)
ADJOINT-BASED SENSITIVITY ANALYSIS FOR REACTOR ACCIDENT CODES. / PARKS, C.V.
, 1985. - (CONF ; CONF-851115-28)
VALIDATION ISSUES FOR DEPLETION AND CRITICALITY ANALYSIS IN BURNUP CREDIT. / PARKS, C.V.
, 2001. - (P00 ; P00-109218)
APPLICATION OF GENERALIZED PERTURBATION THEORY TO FAST REACTOR SAFETY SENSITIVITY STUDIES. / PARKS, C.V.
(CONF ; CONF-790816-29)
ADEQUACY OF THE 123-GROUP CROSS-SECTION LIBRARY FOR CRITICALITY ANALYSES OF WATER-MODERATED URANIUM SYSTEMS. / PARKS, C.V.(et al.)
: NUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission)) , 1995. - (NUREG ; NUREG/CR-6328)
ADJOINT-BASED SENSITIVITY ANALYSIS FOR REACTOR SAFETY APPLICATIONS. / PARKS, C.V.
: Oak Ridge National Laboratory(Oak Ridge National Laboratory) , 1986. - (ORNL ; ORNL/CSD/TM-231)
EVALUATION OF SPENT FUEL ISOTOPICS, RADIATION SPECTRA AND DECAY HEAT USING THE SCALE COMPUTATIONAL SYSTEM. / PARKS, C.V.(et al.)
, 1986. - (CONF ; CONF-8606146-3)
CHARACTERIZATION OF NEUTRON SOURCES FROM SPENT FUEL CASKS. / PARKS, C.V.(et al.)
, 1987. - (CONF ; CONF-871101-49)