{
  "date" : "1997-03-01",
  "identifier_doecontract" : "",
  "subject" : "05 NUCLEAR FUELS; BURNUP; QUANTITATIVE CHEMICAL ANALYSIS; SPENT FUELS; MIXED OXIDE FUELS; URANIUM DIOXIDE; ISOTOPE RATIO; POST-IRRADIATION EXAMINATION; ELECTRON MICROPROBE ANALYSIS; O CODES; V CODES; FORECASTING; FISSILE MATERIALS",
  "description" : "The post irradiation examinations (PIE) were carried out for high burn-up UO{sub 2} spent fuel (3.8%U235, average burn-up:60GWd/t) and mixed oxide (MOX) spent fuel (5.07%Pu, average burn-up:45GWd/t). The PIE includes, (a) isotopic analysis, (b) electron probe microanalysis (EPMA) in pellet cross section and so on. The results of isotopic analyses and EPMA were compared with ORIGEN2/82 and VIM-BURN calculation results. In VIM-BURN calculation, the nuclear data of actinides were proceeded from new data file, JENDL-3.2. The sensitivities of power history and moderator density to nuclides composition were investigated by VIM-BURN calculation and consequently power history mainly effected on Am241 and Am242m and moderator density effected on fissile nuclides. From EPMA results of U and Pu distribution in pellet, VIM-BURN calculation showed reasonable distribution in pellet cross section. (author)",
  "language" : "English",
  "identifier_report" : "JAERI-Conf-97-005; CONF-9611184-; INDC(JPN)-179/U",
  "publisher_sponsor" : "",
  "publisher_country" : "Japan",
  "source" : "JPN; SCA: 050800; PA: JPN-97:009078; EDB-97:143324; SN: 97001866981",
  "purl" : "https://www.osti.gov/etdeweb/servlets/purl/544665",
  "title" : "Isotopic analyses and calculation by use of JENDL-3.2 for high burn-up UO{sub 2} and MOX spent fuels",
  "type" : "Conference",
  "subject_related" : "",
  "relation" : "Conference: 1996 symposium on nuclear data, Tokai (Japan), 21-22 Nov 1996; Other Information: PBD: Mar 1997; Related Information: Is Part Of Proceedings of the 1996 symposium on nuclear data; Iguchi, Tetsuo [Nagoya Univ. (Japan)]; Fukahori, Tokio [eds.]; PB: 332 p.",
  "entry_date" : "2008-02-05",
  "subject_list" : [ "05 NUCLEAR FUELS", "BURNUP", "QUANTITATIVE CHEMICAL ANALYSIS", "SPENT FUELS", "MIXED OXIDE FUELS", "URANIUM DIOXIDE", "ISOTOPE RATIO", "POST-IRRADIATION EXAMINATION", "ELECTRON MICROPROBE ANALYSIS", "O CODES", "V CODES", "FORECASTING", "FISSILE MATERIALS" ],
  "publisher_availability" : "OSTI as DE97758662",
  "rights" : "",
  "announced_date" : "2004-01-23",
  "type_qualifier" : "",
  "has_fulltext" : true,
  "coverage" : "",
  "identifier" : "ON: DE97758662",
  "journal_volume" : "",
  "creator" : "Sasahara, Akihiro; Matsumura, Tetsuo [Central Research Inst. of Electric Power Industry, Komae, Tokyo (Japan). Komae Research Lab.]; Nicolaou, G; Betti, M; Walker, C T",
  "site_ownership_code" : "JPN",
  "osti_id" : "544665",
  "journal_issue" : "",
  "resource_type" : "CONF",
  "format" : "Medium: X; Size: pp. 9-14",
  "journal_name" : [ ],
  "contributing_organizations" : "",
  "citation_location" : "https://www.osti.gov/etdeweb/biblio/544665",
  "publication_year" : 1997,
  "subject_list_commas" : "05 NUCLEAR FUELS, BURNUP, QUANTITATIVE CHEMICAL ANALYSIS, SPENT FUELS, MIXED OXIDE FUELS, URANIUM DIOXIDE, ISOTOPE RATIO, POST-IRRADIATION EXAMINATION, ELECTRON MICROPROBE ANALYSIS, O CODES, V CODES, FORECASTING, FISSILE MATERIALS",
  "publisher" : "",
  "identifier_other" : "Other: ON: DE97758662; TRN: JP9709078",
  "publisher_research" : "Japan Atomic Energy Research Inst., Tokyo (Japan)",
  "creators_list" : [ "Sasahara, Akihiro", "Matsumura, Tetsuo [Central Research Inst. of Electric Power Industry, Komae, Tokyo (Japan). Komae Research Lab.]", "Nicolaou, G", "Betti, M", "Walker, C T" ],
  "doi" : "https://doi.org/"
}