Publications

Miller, David R.; Molecke, Martin A.; Gregson, Michael W.; Brockmann, John E.; Steyskal, Michele S.

Abstract not provided.

Molecke, Martin A.

Abstract not provided.

Lopez Mestre, Carlos L.; Ammerman, Douglas J.; Molecke, Martin A.; Yoshimura, Richard H.; Kalan, Robert K.; Aragon, Mona L.

Abstract not provided.

Brockmann, John E.; Lucero, Daniel A.; Molecke, Martin A.; Borek, Theodore T.

Abstract not provided.

Molecke, Martin A.

Abstract not provided.

Molecke, Martin A.; Sorenson, Ken B.; Borek, Theodore T.

A multinational test program is in progress to quantify the aerosol particulates produced when a high energy density device, HEDD, impacts surrogate material and actual spent fuel test rodlets. This program provides needed data that are relevant to some sabotage scenarios in relation to spent fuel transport and storage casks, and associated risk assessments; the program also provides significant political benefits in international cooperation. We are quantifying the spent fuel ratio, SFR, the ratio of the aerosol particles released from HEDD-impacted actual spent fuel to the aerosol particles produced from surrogate materials, measured under closely matched test conditions. In addition, we are measuring the amounts, nuclide content, size distribution of the released aerosol materials, and enhanced sorption of volatile fission product nuclides onto specific aerosol particle size fractions. These data are crucial for predicting radiological impacts. This document includes a thorough description of the test program, including the current, detailed test plan, concept and design, plus a description of all test components, and requirements for future components and related nuclear facility needs. It also serves as a program status report as of the end of FY 2003. All available test results, observations, and analyses - primarily for surrogate material Phase 2 tests using cerium oxide sintered ceramic pellets are included. This spent fuel sabotage - aerosol test program is coordinated with the international Working Group for Sabotage Concerns of Transport and Storage Casks, WGSTSC, and supported by both the U.S. Department of Energy and Nuclear Regulatory Commission.

Molecke, Martin A.; Sorenson, Ken B.; Gregson, Michael W.

Abstract not provided.

Molecke, Martin A.; Molecke, Martin A.; Yoshimura, Richard H.; Longley, Susan W.

Abstract not provided.

Molecke, Martin A.; Molecke, Martin A.; Bates, Raleigh A.; McConnell, Paul E.; Greene, Steven N.

Abstract not provided.

Molecke, Martin A.; Luna, Robert E.; Vigil, Manuel G.; Molecke, Martin A.; Yoshimura, Richard H.

Abstract not provided.

Krumhansl, James L.; Molecke, Martin A.; Papenguth, Hans W.; Brush, Laurence H.

Backfills have been part of Sandia National Laboratories' [Sandia's] Waste Isolation Pilot Plant [WIPP] designs for over twenty years. Historically, backfill research at Sandia has depended heavily on the changing mission of the WIPP facility. Early testing considered heat producing, high level, wastes. Bentonite/sand/salt mixtures were evaluated and studies focused on developing materials that would retard brine ingress, sorb radionuclides, and withstand elevated temperatures. The present-day backfill consists of pure MgO [magnesium oxide] in a pelletized form and is directed at treating the relatively low contamination level, non-heat producing, wastes actually being disposed of in the WIPP. Its introduction was motivated by the need to scavenging CO{sub 2} [carbon dioxide] from decaying organic components in the waste. However, other benefits, such as a substantial desiccating capacity, are also being evaluated. The MgO backfill also fulfills a statutory requirement for assurance measures beyond those needed to demonstrate compliance with the US Environmental Protection Agency [EPA] regulatory release limits. However, even without a backfill, the WIPP repository design still operates within EPA regulatory release limits.

Krumhansl, James L.; Zhang, Pengchu Z.; Westrich, Henry R.; Bryan, Charles R.; Brady, Patrick V.; Molecke, Martin A.

Conventional performance assessments assume that radioactive {sup 99}Tc travels as a non-sorbing component with an effective K{sub d} (distribution coefficient) of 0. This is because soil mineral surfaces commonly develop net negative surface charges and pertechnetate (TcO{sub 4}), with large ionic size and low electrical density, is not sorbed onto them. However, a variety of materials have been identified that retain Tc and may eventually lead to promising Tc getters. In assessing Tc getter performance it is important to evaluate the environment in which the getter is to function. In many contaminant plumes Tc will only leach slowly from the source of the contamination and significant dilution is likely. Thus, sub-ppb Tc concentrations are expected and normal groundwater constituents will dominate the aquifer chemistry. In this setting a variety of constituents were found to retard TcO{sub 4}: imogolite, boehmite, hydrotalcite, goethite, copper sulfide and oxide and coal. Near leaking tanks of high level nuclear waste, Tc may be present in mg/L level concentrations and groundwater chemistry will be dominated by constituents from the waste. Both bone char, and to a lesser degree, freshly precipitated Al hydroxides may be effective Tc scavengers in this environment. Thus, the search for Tc getters is far from hopeless, although much remains to be learned about the mechanisms by which these materials retain Tc.

Molecke, Martin A.

This report documents the decommissioning and abandonment activities at the Weeks Island Strategic Petroleum Reserve (SPR) site, Iberia Parish, Louisiana, that were concluded in 1999. These activities required about six years of intense operational, engineering, geotechnical, and management support efforts, following initiation of site abandonment plans in 1994. The Weeks Island SPR mine stored about 72.5 million bbl of crude oil following oil fill in 1980--1982, until November 1995, when the DOE initiated oil drawdown procedures, with brine refill and oil skimming, and numerous plugging and sealing activities. About 98% of the crude oil was recovered and transferred to other SPR facilities in Louisiana and Texas; a small amount was also sold. This document summarizes recent pre- and post-closure: conditions of surface features at the site, including the sinkholes, the freeze wall, surface subsidence measurements and predictions; conditions within the SPR mine, including oil recovery, brine filling, and the Markel Wet Drift; risk assessment evaluations relevant to the decommissioning and long-term potential environmental impacts; continuing environmental monitoring activities at the site; and, an overview on the background and history of the Weeks Island SPR facility.