s at the cladding surface has been calculated at the peak power location in the core of a 300-MWe GCFR. ![]() A flux of recoil helium particles as high as 4.2 x 10 10 He/cm 2. The neutron-induced implantation of helium atoms on the exterior surfaces of the cladding of a prototypic gas-cooled fast reactor ( GCFR) has been investigated analytically. Neutron-induced helium implantation in GCFR cladding Each phase represents a distinct area of uncertainty in computing radiation transport from the GCFR core to the plenums, through the upper and lower plenum shields, and ultimately to the prestressed concrete reactor vessel (PCRV) liner: ( 1) the shield heterogeneity phase (2) the exit shield simulation phase (3) the plenum streaming phase and (4) the plenum shield simulation phase This report defines four experiment phases. This report gives the experiment objectives and generic descriptions of experimental configurations for the gas-cooled fast breeder reactor ( GCFR) plenum shield experiment. Requirements for the GCFR plenum streaming experiment These desirable aspects of a GCFR fuel pin can be maintained only as long as axial gas transport paths are available and operating within the fuel pin Consequently, should a breach occur in the cladding, helium flows into the breached fuel pin thereby minimizing fission product contamination of the coolant. In addition, the venting system also maintains the pressure within the fuel pin slightly below (0.3 to 0.5 MPa) the coolant pressure outside the fuel pin. As a result, the internal pressure of a GCFR fuel pin does not increase during irradiation. Each GCFR fuel rod is vented to a manifold whereby gaseous fission products diffusing out of the fuel pin are retained on charcoal traps. The latter design feature brings about improved heat transfer characteristics. The former design feature enables reduction in cladding thickness and prevention of possible creep collapse of the cladding due to the high coolant pressure (8.5 MPa). These unique design features include the use of ( 1) vented and pressure-equalized fuel rods, and (2) ribbed cladding along 75% of the fuel section. The fuel rod design for the Gas Cooled Fast-Breeder Reactor ( GCFR) is similar to that employed for the Liquid Metal Fast Breeder Reactor (LMFBR) with the exception of the unique features inherent to the use of helium as the coolant. Finally, the means by which the plan is being implemented are discussed To ensure that all necessary tasks are covered to achieve these goals, the program plan is broken into a work breakdown structure (WBS). To implement a quantitative risk-based approach in identifying the important technology requirements for each LOP, frequency and consequence-limiting goals are allocated to each. Each LOP provides an independent, sequential, quantifiable risk barrier between the public and the radiological hazards associated with postulated GCFR accidents. The activities under this plan are organized to support six lines of protection (LOPs) for protection of the public from postulated GCFR accidents. This paper presents a summary of the recently revised gas-cooled fast breeder reactor ( GCFR) safety program plan. The conversion and application of these codes for GCFR analyses is the subject of this paper As part of this effort the light water reactor codes, FRAPCON- 1 and FRAP-T5 were converted to model GCFR fuel rod behavior. The Idaho National Engineering Laboratory (INEL) was contracted to review the Preliminary Safety Information Document (PSID) Amendment 10 for Gas-Cooled Fast Reactors ( GCFR). The effect of ribbing, as well as the ribbing process, on the short- and long-term structural performance of fuel-pin cladding is being evaluated via in-reactor and out-of-reactor tests and with the fuel-element modeling code LIFE- GCFR and the finite element program, ADINAĬalculated GCFR fuel rod behavior for steady state and transient operation Studies of the thermodynamics and kinetics of the U-Cs-O system, supplemented by analysis of the results of previously irradiated fuel pins, have led to the incorporation of fuel-design modifications in the F-5 experiment to insure adequate performance of the vented fuel. The fuel pins are presently undergoing interim examination after successfully achieving 4.6 at.% burnup. ![]() It is the largest-scale fuel-pin experiment in the present program and will provide data on the performance of pins and a pin-support structure that are prototypic of the GCFR Demonstration Plant. The F-5 fuel-pin irradiation experiment in EBR-II is a cornerstone of the GCFR program. International Nuclear Information System (INIS) GCFR Fuels and Materials Program at Argonne National Laboratory
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