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Title: Transient fission-gas behavior in uranium nitride fuel under proposed space applications. Doctoral thesis

Technical Report ·
OSTI ID:7281314

In order to investigate whether fission gas swelling and release would be significant factors in a space based nuclear reactor operating under the Strategic Defense Initiative (SDI) program, the finite element program REDSTONE (Routine For Evaluating Dynamic Swelling in Transient Operational Nuclear Environments) was developed to model the 1-D, spherical geometry diffusion equations describing transient fission gas behavior in a single uranium nitride fuel grain. The equations characterized individual bubbles, rather than bubble groupings. This limits calculations to those scenarios where low temperatures, low burnups, or both were present. Instabilities in the bubble radii calculations forced the implementation of additional constraints limiting the bubble sizes to minimum and maximum (equilibrium) radii. The validity of REDSTONE calculations were checked against analytical solutions for internal consistency and against experimental studies for agreement with swelling and release results.

Research Organization:
Air Force Inst. of Tech., Wright-Patterson AFB, OH (United States)
OSTI ID:
7281314
Report Number(s):
AD-A-252577/2/XAB; AFIT/CI/CIA-92-001D
Resource Relation:
Other Information: Thesis (Ph.D.)
Country of Publication:
United States
Language:
English