Appropriate Burnup Measurements for Transportation Burnup Credit

Details

• Creators:
  Lancaster, Dale ; Fuentes, Emilio
• Corporate Creators:
  TRW Inc.
• Corporate Contributors:
  United States. Department of Energy ; U.S. Nuclear Regulatory Commission (NRC)
• Subject/TRT Terms:
  Burnup Casks Chemical Reactivity Nuclear Reactors Temperature Measurement
• Resource Type:
  Memorandum
• Geographical Coverage:
  United States
• Corporate Publisher:
  TRW Environmental Safety Systems, Inc.
• Abstract:
  On May 31, 1995, DOE submitted the "Topical Report on Actinide-Only Burnup Credit for PWR Spent Nuclear Fuel Packages"" to the NRC for approval of a generic methodology to analyze spent fuel packages to gain burnup credit. The methodology will be used by cask vendors who will use various neutronic codes but will follow the same steps. As part of the methodology it is required that a burnup verification measurement be performed. This is consistent with the requirements in the ANSI/ANS-8.17 standard on "Criticality Safety Criteria for the Handling, Storage and Transportation of LWR Fuel Outside Reactors" which states a verification must be performed to take credit for burnup. In the original version of the Topical Report submitted to the NRC the burnup measurement was discussed by using an example detector, the fork detector. Since the measurement of burnup is becoming commercialized by the introduction of a measuring device by BNEL, the Rev. 1 version of the Topical Report (issued around 3/31/97) contains a set of measurement specifications. This paper addresses two of those specifications.
• Content Notes:
  Due to no publication date being included in the report, the date has been estimated using the properties of the report.
• Format:
  PDF
• Collection(s):
  US Transportation Collection
• Main Document Checksum:
  urn:sha256:8066a8a3adab2b783e97870f35936c627dfacc7867f0af434c83fdfa34be0a06
• Download URL:
  https://rosap.ntl.bts.gov/view/dot/56349/dot_56349_DS1.pdf
• File Type:
  [PDF - 229.55 KB ]