{
  "date" : "1991-01-01",
  "identifier_doecontract" : "",
  "subject" : "22 GENERAL STUDIES OF NUCLEAR REACTORS; 42 ENGINEERING; FUEL ASSEMBLIES; FLUID FLOW; CRITICAL HEAT FLUX; CRITICAL VELOCITY; FRICTION FACTOR; MECHANICAL VIBRATIONS; PRESSURE DROP; 220600; 420400; RESEARCH, TEST, TRAINING, PRODUCTION, IRRADIATION, MATERIALS TESTING REACTORS; HEAT TRANSFER AND FLUID FLOW",
  "description" : "Hydraulic and velocity measurment tests were carried out for the KMRR fuel assembly. Two types of the KMRR fuel assembly are consist of longitudinally finned rods. Experimental data of the pressure drops and friction factors for the KMRR fuel assemlby were produced. The measurement technique for the turbulent flow structure in subchannels using the LDV was obtained. The measurement of the experimental constant of the thermal hydraulic analysis code was investigated. The results in this study are used as the basic data for the development of an analysis code. The measurement technique acquired in this study can be applied to the KMRR thermal hydraulic commissioning test and development of the domestic KMRR fuel fabrication. (Author).",
  "language" : "Korean",
  "identifier_report" : "KAERI/RR-961/90",
  "publisher_sponsor" : "",
  "publisher_country" : "Korea, Republic of",
  "source" : "INIS; SCA: 220600; 420400; PA: AIX-23:015080; SN: 92000646949",
  "purl" : "",
  "title" : "Fluid flow test for KMRR fuel assemblies",
  "type" : "Technical Report",
  "subject_related" : "",
  "relation" : "Other Information: PBD: Jan 1991",
  "entry_date" : "2008-02-12",
  "subject_list" : [ "22 GENERAL STUDIES OF NUCLEAR REACTORS", "42 ENGINEERING", "FUEL ASSEMBLIES", "FLUID FLOW", "CRITICAL HEAT FLUX", "CRITICAL VELOCITY", "FRICTION FACTOR", "MECHANICAL VIBRATIONS", "PRESSURE DROP", "220600", "420400", "RESEARCH, TEST, TRAINING, PRODUCTION, IRRADIATION, MATERIALS TESTING REACTORS", "HEAT TRANSFER AND FLUID FLOW" ],
  "publisher_availability" : "OSTI; NTIS (US Sales Only); INIS",
  "rights" : "",
  "announced_date" : "2005-06-30",
  "type_qualifier" : "",
  "has_fulltext" : false,
  "coverage" : "",
  "identifier" : "ON: DE92615115",
  "journal_volume" : "",
  "creator" : "Chung, Moon Ki; Yang, Sun Kyu; Chung, Chang Hwan; Chun, See Young; Song, Chul Hha; Jun, Hyung Gil; Chung, Heung Joon; Won, Soon Yeun; Cho, Young Rho; Kim, Bok Deuk [Korea Atomic Energy Research Inst., Daeduk (Korea, Republic of)]",
  "site_ownership_code" : "INIS",
  "osti_id" : "10113216",
  "journal_issue" : "",
  "resource_type" : "RPRT",
  "format" : "Medium: X; Size: 134 p.",
  "journal_name" : [ ],
  "contributing_organizations" : "",
  "citation_location" : "https://www.osti.gov/etdeweb/biblio/10113216",
  "publication_year" : 1991,
  "subject_list_commas" : "22 GENERAL STUDIES OF NUCLEAR REACTORS, 42 ENGINEERING, FUEL ASSEMBLIES, FLUID FLOW, CRITICAL HEAT FLUX, CRITICAL VELOCITY, FRICTION FACTOR, MECHANICAL VIBRATIONS, PRESSURE DROP, 220600, 420400, RESEARCH, TEST, TRAINING, PRODUCTION, IRRADIATION, MATERIALS TESTING REACTORS, HEAT TRANSFER AND FLUID FLOW",
  "publisher" : "",
  "identifier_other" : "Other: ON: DE92615115; TRN: KR9100115015080",
  "publisher_research" : "Korea Atomic Energy Research Inst., Daeduk (Korea, Republic of)",
  "creators_list" : [ "Chung, Moon Ki", "Yang, Sun Kyu", "Chung, Chang Hwan", "Chun, See Young", "Song, Chul Hha", "Jun, Hyung Gil", "Chung, Heung Joon", "Won, Soon Yeun", "Cho, Young Rho", "Kim, Bok Deuk [Korea Atomic Energy Research Inst., Daeduk (Korea, Republic of)]" ],
  "doi" : "https://doi.org/"
}