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Title: Fast Flux Test Facility (FFTF) Shutdown Activities


No abstract prepared.

Publication Date:
Research Org.:
Sponsoring Org.:
USDOE Office of Environmental Management (EM) (US)
OSTI Identifier:
Report Number(s):
HNF-8279-FP, Rev.0
TRN: US0301698
DOE Contract Number:
Resource Type:
Resource Relation:
Conference: Conference title not supplied, Conference location not supplied, Conference dates not supplied; Other Information: PBD: 1 Jun 2001
Country of Publication:
United States

Citation Formats

BREHM, W.F. Fast Flux Test Facility (FFTF) Shutdown Activities. United States: N. p., 2001. Web.
BREHM, W.F. Fast Flux Test Facility (FFTF) Shutdown Activities. United States.
BREHM, W.F. 2001. "Fast Flux Test Facility (FFTF) Shutdown Activities". United States. doi:.
title = {Fast Flux Test Facility (FFTF) Shutdown Activities},
author = {BREHM, W.F.},
abstractNote = {No abstract prepared.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = 2001,
month = 6

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  • The reliability analysis of the Fast Flux Test Facility reactor shutdown system was reevaluated. Failure information based on five years of plant operating experience was used to verify original reliability numbers or to establish new ones. Also, system modifications made subsequent to performance of the original analysis were incorporated into the reevaluation. Reliability calculations and sensitivity analyses were performed using a commercially available spreadsheet on a personal computer. The spreadsheet was configured so that future failures could be tracked and compared with expected failures. A number of recommendations resulted from the reevaluation including both increased and decreased surveillance intervals. Allmore » recommendations were based on meeting or exceeding existing reliability goals. Considerable cost savings will be incurred upon implementation of the recommendations.« less
  • The three public utilities serving the Tri-Cities area of central Washington State have entered into a Cooperative Agreement with the Department of Energy to explore the feasibility of a utility-owned power addition to the Fast Flux Test Facility (FFTF). This paper describes the results of the design and economic studies completed to data, which indicate that the addition of steam generators and a 120 MWe power plant to the FFTF is both technically feasible and economically attractive compared to alternative power sources. 1 ref., 3 figs., 2 tabs.
  • A cobalt test assembly containing yttrium hydride pins for neutron moderation was irradiated in the Fast Flux Test Facility during Cycle 9A for 137.7 equivalent full power days at a power level of 291 MW. The 36 test pins consisted of a batch of 32 pins containing cobalt metal to produce Co-60, and a set of 4 pins with europium oxide to produce Gd-153, a radioisotope used in detection of the bone disease Osteoporosis. Post-irradiation examination of the cobalt pins determined the Co-60 produced with an accuracy of about 5%. The measured Co-60 spatially distributed concentrations were within 20% ofmore » the calculated concentrations. The assembly average Co-60 measured activity was 4% less than the calculated value. The europium oxide pins were gamma scanned for the europium isotopes Eu-152 and Eu-154 to an absolute accuracy of about 10%. The measured europium radioisotope and Gd-153 concentrations were within 20% of calculated values. In conclusion, the hydride assembly performed well and is an excellent vehicle for many Fast Flux Test Facility isotope production applications. The results also demonstrate that the calculational methods developed by the Westinghouse Hanford Company are very accurate. 4 refs., 3 figs., 1 tab.« less
  • The Fast Flux Test Facility (FFTF) is a liquid-metal-cooled test reactor located on the Hanford Site. The FFTF is the only reactor of this type designed and operated with the intent of meeting the licensing requirements of the Nuclear Regulatory Commission (NRC). Unique characteristics of the FFTF that present special challenges related to leak rate testing include thin wall containment vessel construction, cover gas systems that penetrate containment, and a low-pressure design basis accident. The successful completion in 1986 of the third FFTF Integrated Leak Rate Test (ILRT) five days ahead of schedule and 10% under budget was a majormore » achievement for the Westinghouse Hanford Company. The success of this operational safety test was due in large part to a special local area network (LAN) of three IBM PC/XT computers that monitored the sensor data, calculated the containment vessel leak rate, and displayed test results. The multiple computer configuration allowed continuous monitoring of the progress of the test independently of the data acquisition and analysis functions, and also provided improved overall system reliability by permitting immediate switching of computers if the equipment failed. 5 refs., 8 figs.« less
  • The relatively large irradiation volume, instrumentation capabilities, and fast neutron flux associated with the Fast Flux Test Facility (FFTF) make this reactor an ideal test bed for fusion materials and components irradiations. Significant fusion materials irradiations are presently being performed in the Materials Open Test Assembly (MOTA) in FFTF. The MOTA is providing a controlled temperature and high neutron flux environment for such materials as the low activation alloys, copper alloys, ceramic insulators, and high heat flux materials. Conceptual designs utilizing the versatile MOTA irradiation vehicle have been developed to investigate irradiation effects on the mechanical and tritium breeding behaviorsmore » of solid breeder materials. More aggressive conceptual designs have also been developed to irradiate solid breeder blanket submodules in the FFTF. These specific component test designs will be presented and their potential roles in the development of fusion technology discussed.« less