Fuel Behavior

Tahle 2. Potential U minerals of interest to spent fuel behavior in a geological repository... 

Une, K., Hirai, M., Nogita, K., Hosokawa, T., Suzawa, Y., Shimizu, S. Etoh, Y. 2000. Rim structure formation and high bumup fuel behavior of large-grained U02 fuels. Journal of Nuclear Materials, 278, 54-63. 

The PIE of fuel subassemblies of PNC316 steel and PNC 1520 advanced austenitic stainless steel inadiated in FFTF has been successfully completed. The 2nd shipment of irradiated fuel materials to OEC was conducted to take a further investigation of high bumup fuel behavior. 

Allen, M. D., Stockman, H. W., Reil, K. O., Grimley, A. J. Fission product release and fuel behavior in irradiated light water reactor fuel under severe accident conditions The ST-1 experiment. Nucl. Technology 92, 214—228 (1990)... 

Japan. Six mixed nitride fuel pins were fabricated for irradiation tests in JMTR and JOYO [7.56. 7.61], The irradiation in JOYO started in August, 1994, for a target bura-up of about 4.5 at. % (2 fuel pins). With regard to the fuel cycle, an innovative concept has been proposed, involving fused salt electroreflning and refabrication of sphere-pac fuel. At present the results of PIE of 4 pins are under analysis, but the features of fuel behavior observed in irradiation tests are briefly summarized as follows [7.56] ... 

In the pin design for the first core loading a fission gas plenum was not foreseen because of both limited design experience and inadequate knowledge of fuel behavior under irradiation. As a result, the gas pressure reached 30 MPa and caused fuel leakage. Ten SAs at the peak bum-up values from 2.2 to 6.7% at. were selected for PIE. Failed fuel pins were found in six of the SAs. Two of these 6 SAs at bum-ups of 4.9% at. contained pins with cracked cladding. Each of the other four SAs, at bum-ups of 5.6, 6.1, 6.6, 6.75% at.,... 

Williamson, R.L., Hales, J.D. et al 2012. Multidimensional multiphysics simulation of nuclear fuel behavior, Journal of Nuclear Materials 423 149-163. 

Sato, I., et al., 2004. Transient fuel behavior and failure condition in the CABRI-2 experiments. Nuclear Technology 145 (1), 115—137. 

S. Higuchi, S. Sakurai, T. Ishida, A study of fuel behavior in an SCWR core with high power density, in Proc. ICAPP 07, May 13—18, 2007. Nice, France, Paper 7206. 

B, Rivard and F. E. Haskin, "LWR Meltdown Analyses and Uncertainties," ANS/ENS Topical Meeting on Reactor Safety Aspects of Fuel Behavior, Sun Valley, ID, (August 2-6, 1981). 

M. D. Allen, H. W. Stockman, K. 0. Reil, J. W. Fisk, Fission Product Release and Fuel Behavior of Irradiated Light Water Reactor Fuel Under Severe Accident Conditions The ACRR ST-1 Experiment , NUREG/CR-5345, SAND89-0308, Sandia National Laboratories, November 1991. 

M. Suzuki, H. Saitou and T. Iwamura, Analysis of MOX Fuel Behavior in Reduced Moderation Water Reactor by Fuel Performance Code FEMAXI-RM, Nuclear Engineering... 

These characteristics define the state of the fuel pin for mechanical calculations. Temperature distribution and voidage redistribution are closely linked (5) so these, together with swelling and fission product distribution, can be conveniently simulated by fuel behavior computer... 

In the reactor, the clad is subjected to a very complex set of phenomena, particularly when the power is cycled. The most important parameters alfecting clad performance are thermal stress cycling and stress concentrations caused by nonuniform axial and nonaxisymmetric fuel behavior. Both these factors are expected to be less damaging in sodium-cooled reactors than in gas- or water-cooled systems, because high coolant pressures force the clad to collapse onto the fuel and follow its movements as the power varies. They can, however, still significantly affect fuel pin life. 

The lower stress region is the most important with respect to fuel behavior. When some of the uranium is substituted with plutonium,... 

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