B.J. Makenas's scientific contributions
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Publications (16)
Sludge samples from the canisters in the Hanford K East Basin fuel storage pool have been retrieved and analyzed. Both chemical and physical properties have been determined. The results are to be used to determine the disposition of the bulk of the sludge and to assess the impact of residual sludge on dry storage of the associated intact metallic u...
Characterization is in progress for the N Reactor fuel stored in the Hanford K Basins. These activities` support the strategy for removal of fuel from the basins and storage of fuel in a dry condition at an area remote from the Columbia River. This strategy currently consists of placing fuel in a Multi-Canister Overpack (MCO), drying the fuel while...
Efforts are under way to gather data on the condition of the metal fuel and associated sludge stored in the water-filled Hanford K Basins. Most of the current data gathering activities are being performed in the basins without fuel movement. These techniques include a video survey of open storage canisters, determination of water/gas levels in seal...
The Hanford K Basins contain roughly 2,000 tons of uranium metal fuel previously irradiated in N Reactor. Current plans call for the fuel to be moved to a new storage location in the next few years. This paper describes near term activities to gather data on the mechanical condition and chemical state of the fuel and associated sludge. These on-goi...
The effects of design and operating parameters on mixed-oxide fuel pin irradiation performance were established for the Hanford Engineering Development Laboratory (HEDL) advanced oxide EBR-II test series. Fourteen fuel pins breached in-reactor with reference 316 SS cladding. Seven of the breaches are attributed to FCMI. Of the remaining seven breac...
Mixed uranium-plutonium oxide fuel pins with candidate ferritic alloy cladding have been irradiated in the Experimental Breeder Reactor II (EBR-II) to evaluate performance for possible liquid-metal reactor (LMR) application. Ferritic alloys are of considerable interest in LMRs because of their resistance to irradiation-induced swelling. Ferritic al...
The use of 316 stainless steel (SS) for Liquid Metal Fast Reactor applications is limited because of its tendency to swell significantly under neutron irradiation. Consequently, a number of alloys have been proposed as advanced cladding materials including precipitation hardened alloys, ferritic materials, and titanium modified versions of austenit...
Swelling behavior has been evaluated for irradiated 20% CW 316 stainless steel used as cladding material for mixed-oxide fuel pins in EBR-II. This behavior has been compared statistically with the behavior of a large number of specimens which were irradiated without adjacent fuel in the same reactor. In spite of the chemical environment and stresse...
Experiments have been conducted which assess the effects on fuel pin performance of specific minor variations from nominal in both fuel pellet size and pellet composition. Such pellets are generally referred to in the literature as rogue pellets. The effect of these rogue pellets on fuel pin and reactor performance is shown to be minimal.
Several types of stainless steel (304, 316, 316-20% Cold Worked, and 316 Titanium stabilized 20% CW) have been used as cladding for mixed oxide (U, Pu)O/sub 2/ fuel pins irradiated in EBR-II. All of the materials have performed satisfactorily in their respective experimental subassemblies but significant differences in swelling and inelastic strain...
This Sampling and Analysis Plan (SAP) details the sampling and analyses to be performed on fuel canisters transferred to the Weasel Pit of the 105-KW fuel storage basin. The radionuclide content of the liquid and gas in the canisters must be evaluated to support the shipment of fuel elements to the 300 Area in support of the fuel characterization s...
The Characterization of Spent Nuclear Fuel in the sealed K West canisters involves four steps, (1) sampling of gas/liquid, (2) ``Lift-and-Look`` visual examinations of fuel elements, (3) sampling of canister sludge, and (4) retrieving fuel for hot cell examinations. This document indicates the choices of particular canisters that were examined duri...
Mixed uranium-plutonium oxide fuel pins with candidate ferritic alloy cladding have been irradiated in the EBR-II to evaluate performance for possible Liquid Metal Reactor (LMR) application. Ferritic alloys are of considerable interest in LMR's because of their resistance to irradiation induced swelling which, in the case of austenitic alloys, has...
Iron-nickel base, precipitation-strengthened alloys, IN-706 and PE-16, advanced alloy cladding considered for breeder reactor applications, were irradiated in mixed-oxide fuel pins in the HEDL-P-60 subassembly in EBR-II. Initial selection of candidate advanced alloys was done using only nonfueled materials test results. However, to establish the pe...
Citations
... 0.0 02-0.0 09%P) achieved peak fuel burnups ranging from 101-188 GWd/t in FFTF with corresponding peak displacement damages of ∼54 -110 dpa [39] . The swelling data of D9 variants irradiated as cladding and duct in EBR-II [60] and FFTF [61] is plotted in Fig. 16 [59] . It is well known that at very high levels of swelling, the irradiation induced hardening in austenitic stainless steels is reversed leading to softening along with drastic ductility reductions [62][63][64] , often resulting in failure of clad or wrapper under low load handling. ...
... dmgd. fuel;Makenas et al. 1998 Floor/can sludge/fuel; 28-mo stl.;Delegard et al. 2005 Split from Weasel Pit KES-Q-17;Makenas et al. 1996 See Delegard et al. (2011 and documents referenced therein for further descriptions of most samples and references cited in this table for others. ...
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