Power coupling in TREAT M-Series: New experimental results from M7CAL and updated analyses
Experiments and methods used to determine power coupling of test fuel to the TREAT reactor during six recent metal-fueled sodium loop tests (M2-M7) are described. Previously reported calibration work on a three-pin test configuration with uranium-fissium fuel is updated (M2CAL). Additional results on a two-pin test configuration with the Integral Fast Reactor (IFR) reference fuel (uranium-zirconium and uranium-plutonium-zirconium) are reported (M7CAL). The peak axial low-level, steady-state (LLSS) fresh fuel pin power coupling factors for the IFR fuel compositions were determined from radiochemical analysis of fuel segments. A large data base of uranium-zirconium neutron flux monitor wire measurements were compiled to extend the fuel measurements to high-power transient conditions by comparing the measured power couplings from high and low-power wire irradiations. Power coupling results were obtained in both a full-slotted and a half-slotted TREAT core configuration. Relative power coupling measurements are compared to calculations for the three different types of fuel; U/Fs, U/Zr and U/Pu/Zr. Estimates of power coupling including corrections accounting for the effect on the power coupling of isotopic depletion and fuel swelling as the fuel undergoes burnup are presented for planning and analysis of tests M5, M6 and M7.
- Research Organization:
- Argonne National Lab., IL (United States)
- Sponsoring Organization:
- USDOE
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 714162
- Report Number(s):
- ANL-IFR--86; ON: TI88026696
- Country of Publication:
- United States
- Language:
- English
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