In-plant test measurements for spent fuel storage at Morris Operation. Volume 2. Fuel bundle radiation levels

Technical Report · Tue Sep 01 00:00:00 EDT 1981

DOI:https://doi.org/10.2172/5295958· OSTI ID:5295958

Strickler, H R; Eger, K J

This volume is one of a series of topical reports that summarize task activities and accomplishments for engineering and test support in the potential application of Morris Operation to the DOE Away-From-Reactor Spent Fuel Storage Program. Gamma exposure rates near spent fuel were measured in both air and water and are reported in this volume. These rates are compared with exposure rates calculated from parameters routinely supplied by the utility (i.e. initial enrichment, average power density, burnup and decay time). The ORIGEN and QAD-F computer codes were used for the calculation. For measurements, an apparatus was made to hold a fuel bundle and an ion chamber underwater in any of several fixed geometries. A diving bell sized to fit ovr both the fuel and detector was used for in-air measurements, because the water around the fuel could be displaced downward with compressed air. Maximum exposure rates varied from 36,000 R/h next to a 3.5 year old PWR bundle with a 30,000 MWD/MT burnup, to 40 R/h for a 10.5 year old BWR bundle with a burnup by only 180 MWD/MT. Exposure rates in air were only slightly higher than those in water for positions close to the bundles. Farther away where the water shielding was greater the difference was also greater. Reasonable agreement was seen between calculated and measured values (i.e. within +- 50%) for cases where scattering was of secondary importance. The quality of the agreement reflects the detail considered in setting up the geometry for the computer runs.

• Research Organization: General Electric Co., San Jose, CA (USA). Nuclear Fuel and Services Div.
• DOE Contract Number: AC09-81SR10959
• OSTI ID: 5295958
• Report Number(s): NEDG-24922-2; ON: DE82013711; TRN: 82-012822
• Country of Publication: United States
• Language: English

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
AWAY-FROM-REACTOR STORAGE
DOSE RATES
MIDWEST FUEL RECOVERY PLANT
AIR
BURNUP
BWR TYPE REACTORS
ENGINEERING
EXPERIMENTAL DATA
FUEL POOLS
GAMMA RADIATION
PWR TYPE REACTORS
RADIATION DOSES
RADIATION MONITORING
SPENT FUELS
WATER
DATA
DOSES
ELECTROMAGNETIC RADIATION
ENERGY SOURCES
FLUIDS
FUEL REPROCESSING PLANTS
FUELS
GASES
HYDROGEN COMPOUNDS
INFORMATION
IONIZING RADIATIONS
MATERIALS
MONITORING
NUCLEAR FACILITIES
NUCLEAR FUELS
NUMERICAL DATA
OXYGEN COMPOUNDS
RADIATIONS
REACTOR MATERIALS
REACTORS
SPENT FUEL STORAGE
STORAGE
WATER COOLED REACTORS
WATER MODERATED REACTORS
050900* - Nuclear Fuels- Transport
Handling
& Storage
054000 - Nuclear Fuels- Health & Safety