rdf-syntax-grammar
mods:
  schema location: http://www.loc.gov/mods/v3 http://www.loc.gov/standards/mods/v3/mods-3-2.xsd
  title info:
    title: BWR anticipated transients without scram in the MELLLA+ expanded operating domain
  title info:
    title: Boiling Water Reactor anticipated transients without scram in the MELLLA+ expanded operating domain
  name:
    name part: Cheng, Lap-Yan
    role:
      role term: creator
    role:
      role term: author.
  name:
    name part: U.S. Nuclear Regulatory Commission
    name part: Office of Nuclear Regulatory Research,
    role:
      role term: issuing body.
  name:
    name part: U.S. Nuclear Regulatory Commission
    name part: Division of Systems Analysis,
    role:
      role term: sponsoring body.
  name:
    name part: Brookhaven National Laboratory
  type of resource: text
  genre: bibliography
  origin info:
    place:
      place term: dcu
    date issued: 2015
    issuance: monographic
  language:
    language term: eng
  physical description:
    form: remote
    extent: 1 online resource (4 volumes) : color illustrations
  table of contents: Part 1 : Model development and events leading to instability -- Part 2 : Sensitivity studies for events leading to instability -- Part 3 : Events leading to emergency depressurization -- Part 4 : Sensitivity studies for events leading to emergency depressurization.
  note: Lap-Yan Cheng [and five others].
  note: Title from title screen (viewed on July 23, 2015).
  note: "Manuscript completed: April 2014; Date published: June 2015."
  note: "NUREG/CR-7179, BNL-NUREG-105325-2014"--Part 1.
  note: "NUREG/CR-7180, BNL-NUREG-105327-2014"--Part 2.
  note: "NUREG/CR-7181, BNL-NUREG-105328-2014"--Part 3.
  note: "NUREG/CR-7182, BNL-NUREG-105330-2014"--Part 4.
  note: V6150 / F6018
  note: Includes bibliographical references.
  subject:
    geographic code: n-us---
  subject:
    topic: Boiling water reactors
    topic: Performance
    topic: Testing
    topic: Computer simulation
  subject:
    topic: Boiling water reactors
    topic: Performance
    topic: Technological innovations
  subject:
    topic: Nuclear power plants
    topic: Safety measures
    topic: Computer programs
  subject:
    topic: Nuclear power plants
    topic: Safety measures
    topic: Testing
  classification: Y 3.N 88:25/7179-7182
  related item:
    title info:
      title: BWR anticipated transients without scram in the MELLLA+ expanded operating domain
    identifier: (OCoLC)911930251
  identifier: https://purl.fdlp.gov/GPO/gpo59253
  record info:
    record content source: GPO
    record creation date: 150724
    record change date: 20211120173219.0
    record identifier: in00003599964
    language of cataloging:
      language term: eng