Skip to main content
U.S. Department of Energy
Office of Scientific and Technical Information

Quarterly Progress Report on Fission Product Behavior in LWRs for the Period April-June 1978

Technical Report ·
DOI:https://doi.org/10.2172/6515189· OSTI ID:6515189
Analysis of data obtained during High Burnup Fuel Test 12 (HBU-12) is complete; this test was conducted to determine the gap inventories of cesium and iodine by purging a selected H.B. Robinson fuel rod segment with purified helium. Total release of both species was virtually identical when expressed as percent of total inventory. In addition, it was possible to estimate the extent to which diffusion of cesium from the pellet matrix augmented the gap inventory of this species. Correction of the data for this contribution indicated that the gap inventory of cesium for this H.B. Robinson fuel rod amounted to 0.30% of total cesium inventory, as compared with a value of 0.25% which was inferred from determinations of xenon gap inventory made earlier. Preparations are being made for the conduct of the High Temperature Test Series and for tests with Boiling Water Reactor (BWR) fuel from Peach Bottom-2. Gross gamma activity scans of the Peach Bottom fuel rod which will be employed in the latter tests indicate a buildup of cesium at pellet-pellet interfaces; this suggests that the gap inventory of cesium and iodine is significantly higher than that found in the H.B. Robinson rods which have been used in the High Burnup Fuel Test Series. Two preliminary designs of the Fission Product Transport Test Facility (FPTTF) have been developed; one of these is for a facility which is capable of operation with steam at 1600/sup 0/C, and the other with steam at 1000°C. Cost/benefit analyses were made which supported further development of only the 1000°C steam capability.
Research Organization:
Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
Sponsoring Organization:
USDOE; USNRC
DOE Contract Number:
W-7405-ENG-26;
Other Award/Contract Number:
DOE-40-551-75
DOE-40-552-75
NRC-FIN-B0127
OSTI ID:
6515189
Report Number(s):
ORNL/NUREG/TM--242; NUREG/CR-0370
Country of Publication:
United States
Language:
English