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: Assessment of the fingerprinting method for spent fuel verification in MACSTOR KN-400 CANDU dry storage
  name:
    name part: Gowthahalli Chandregowda, Nandan.
    role:
      role term: creator
  name:
    name part: Charlton, William S.
    role:
      role term: thesis advisor.
  name:
    name part: Chirayath, Sunil S.
    role:
      role term: thesis advisor.
  type of resource: text
  genre: bibliography
  origin info:
    place:
      place term: txu
    date issued: 2012
    issuance: monographic
  language:
    language term: eng
  physical description:
    form: remote
    extent: 1 online resource.
  abstract: The Korea Hydro and Nuclear Power has built a new modular type of dry storage facility, known as MACSTOR KN-400 at Wolsong reactor site. The building has the capacity to store up to 24000 CANDU spent fuel bundles in a 4 rows by 10 columns arrangement of silos. The MACSTOR KN-400 consists of 40 silos; each silo has 10 storage baskets, each of which can store 60 CANDU spent fuel bundles. The development of an effective method for spent fuel verification at the MACSTOR KN-400 storage facility is necessary in order for the International Atomic Energy Agency (IAEA) to meet with safeguards regulations. The IAEA is interested in having a new effective method of re-verification of the nuclear material in the MACSTOR KN-400 dry storage facility in the event of any loss of continuity of knowledge, which occasionally happens when the installed seals fail. In the thesis work, MCNP models of central and corner structures of the MACSTOR KN-400 facility are developed, since both have different types of re-verification system. Both gamma and neutron simulations were carried out using the MCNP models developed for MACSTOR KN-400. The CANDU spent fuel bundle with discharge burnup of 7.5 GWD/t (burned at specific power of 28.39 MW/t) and 10 years cooled was considered for radiation source term estimation. For both the structures, MCNP simulations of gamma transport were done by including Cadmium-Zinc-Telluride (CZT) detector inside the re-verification tube. Gamma analyses for different spent fuel bundle diversion scenarios were carried out. It was observed that for diversion scenarios wherein the bundles are removed from the inner portions of the basket (opposite side of the collimator of the re-verification tube), it was difficult to conclude whether diversion has taken place based on the change in gamma radiation signals. Similar MCNP simulations of neutron transport were carried out by integrating helium-3 detector inside the re-verification tube and the results obtained for variou…
  note: "Major Subject: Nuclear Engineering"
  note: Electronic resource.
  note: Master of Science Texas A&M University 2012 http://hdl.handle.net/1969.1/ETD-TAMU-2012-08-11697
  note: Includes bibliographical references.
  note: Text (Thesis)
  subject:
    topic: Major Nuclear Engineering
  subject:
    topic: Gamma
  subject:
    topic: MACSTOR KN-400
  subject:
    topic: CANDU
  subject:
    topic: Neutron
  identifier: http://hdl.handle.net/1969.1/ETD-TAMU-2012-08-11697
  record info:
    record content source: TXA
    record creation date: 121116
    record change date: 20150922143612.0
    record identifier: in00002755604