R. A. Dewberry and S. R. Salaymeh
Westinghouse Savannah River Company
Aiken SC 29808

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The Analytical Development Section of SRTC was requested by the Facilities Disposition Division (FDD) of the Savannah River Site to determine the holdup of enriched uranium in the 321-M facility as part of an overall deactivation project of the facility. The 321-M facility was used to fabricate enriched uranium fuel assemblies, lithium-aluminum target tubes, neptunium assemblies, and miscellaneous components for the production reactors. The results of the holdup assays are essential for determining compliance with the solid waste Waste Acceptance Criteria, Material Control & Accountability, and to meet criticality safety controls. Three measurement systems were used to determine highly enriched uranium (HEU) holdup. One is a portable HPGe detector and EG&G DartÔ system that contains high voltage power supply and signal processing electronics. A personal computer with Gamma-Vision software was used to provide space to store and manipulate multiple 4096-channel g-ray spectra. The second is a 2" x 2" NaI crystal with an MCA that uses a portable computer with a Canberra NaI+ card installed. This card converts the PC to a full function MCA and contains the ancillary electronics, high voltage power supply, and amplifier required for data acquisition. The third is a Canberra Q² waste assay system. This report covers holdup measurements on the A-Lathe that was used to machine uranium-aluminum-alloy (U-Al). Our results indicated that the lathe contained more than the limits stated in the Waste Acceptance Criteria (WAC) for the solid waste E-Area Vaults. Thus the lathe was decontaminated three times and assayed four times in order to bring the amounts of uranium to an acceptable content. This report will discuss the methodology, Non-Destructive Assay (NDA) measurements, and results of the U-235 holdup on the lathe. The reported holdup value on the lathe is 43± 13 g, and the reported values of contamination removed from the lathe and packaged as solid waste is 90± 40 g.

The 321-M facility at the Savannah River Site was used to fabricate enriched uranium fuel assemblies, lithium-aluminum target tubes, neptunium assemblies, and miscellaneous components for the production reactors. The facility operated for 25 years. During this time thousands of uranium-aluminum-alloy (U-Al) fuel tubes were produced. After the facility ceased operations in 1995 all of the easily accessible U-Al was removed from the building, and only residual amounts remained. The bulk of this residue is located in the equipment that generated and handled small U-Al particles and the exhaust systems for this equipment (e.g., Chip compactor, casting furnaces, log saw, lathes A & B, cyclone separator, Freonä cart, riser crusher, …etc). ¹

U-235 holdup measurements were performed in 1995 and documented in technical report WSRC-TR-95-0492.² The holdup values reported in WSRC-TR-95-0492 were only best estimates, due to lack of time for conducting the measurements and analysis. Therefore Facilities Decontamination Division (FDD) has requested technical assistance from the Analytical Development Section (ADS) of the Savannah River Technology Center (SRTC) to determine the holdup of enriched uranium in the 321-M facility, as part of an overall deactivation project of the facility.³ This project includes the dismantling and removal of all held-up HEU to the extent practical. ADS conducted holdup assays to quantify the amount of HEU on all components removed from the facility prior to placement in B-25 containers. The U-235 holdup in any single component of process equipment must not exceed a 50 g in order to meet the B-25 limit.⁴ This limit was imposed to meet criticality requirements of the solid waste E-Area Low Level Vaults. Thus the holdup measurements are used as guidance to determine if further decontamination of equipment is needed to ensure that the quantity of ²³⁵U does not exceed the 50 g limit. The results of the holdup assays are essential for determining compliance with the solid waste Waste Acceptance Criteria, Material Control & Accountability, and to ensure that criticality safety controls are not exceeded.

This report covers holdup-measurements on A-Lathe that was used for the machining of uranium aluminum alloy (U-Al) castings. Our results indicate a total amount of (43+13) g enriched uranium residue holdup on A-lathe. This determination (including uncertainty that exceeds the 50-g criticality limit) was accepted⁵ after multiple decontamination attempts and after four different assays. This report discusses the assays, which were made in several acquisition configurations, assumptions, calculations, and results to determine the total holdup of HEU residue on the A-lathe.

A 2" x 2" NaI detector system was used to conduct NDA measurements of HEU holdup on the lathe. The detector system uses a 2" x 2" NaI crystal with a multi-channel analyzer (MCA) that uses a portable computer with a Canberra NaI+ card installed. This card converts the personal computer to a full function MCA and contains the ancillary electronics, high voltage power supply, and amplifier required for data acquisition.⁶ The holdup assays were performed by an iterative assay, decontaminate, assay process that started in December 2000 and continued until June 2001. In all, we performed four successive assays and three decontaminations in order to obtain a satisfactory measurement.^7-9 In the remainder of this paper we describe the acquisitions and calculations to determine HEU content.

The initial 32 spectra acquired on December 4, 2000 were obtained in three distinct configurations. One configuration was a far field at a range of 24 inches or 79 inches. The second configuration was a close field at a distance of eight inches, and the third configuration was at contact. We calculated the measured ²³⁵U masses for each acquisition and compared results to arrive at applicable conclusions. The acquisitions are listed in Table 1. The second column in Table 1 includes a very short description of the detector location and the acquisition configuration. A background spectrum is shown in Figure 1. Figure 2 is a typical NaI close-coupled spectrum.

The region of interest of the 186 keV peak from ²³⁵U decay is shown in red in both spectra of Figures 1 and 2. The two peaks near 600 and 700 kev in Figure 2 represent g-rays from the daughter products from decay of naturally-occurring ²³²Th. We confirm this designation later in this report using a spectrum acquired with the portable high purity germanium detection system.

The first four spectra in Table 1 were taken in the far-field configuration at a distance of 24 inches. Using a point source assumption, the observed masses for each of these four were calculated by

[²³⁵U] = (K_p)(d)²(measured cps) = (0.000126)(24)²(cps), (1)

where the first factor is the point source calibration constant in units of g-sec/in² for the

2" x 2" NaI detector with one inch recess in the steel-clad Pb shield.⁶ The point source values tabulated for the first four acquisitions are a measure of the ²³⁵U content of the two ends of the lathe and of the back side of the lathe divided into two segments. Each of these four acquisitions indicates only 1 to 2 grams of residue on the ends and back panel. The front of the lathe, which we expected to contain the bulk of the HEU residue, was taken at a range of 79 inches in acquisition 22 of Table 1. Our point source assay of the front indicates 75 grams of residue, as shown in Table 1.

We performed an alternate calculation assuming an area source configuration from each of the acquisitions 1 – 4 and 22. For these calculations we used equation (2)

[²³⁵U] = (K_a)A(measured cps) = (0.000137)(501)(cps), (2)

where K_a is the area source calibration constant, and the effective area of the NaI detector at a range of 24 inches is 501 in² (reference 7). The area source calculations for the first four spectra are tabulated in the last column of Table 1, and are in excellent agreement with the point source calculations. At a range of 79 inches we determined that the detector is viewing an effective area of 5420 square inches.⁷ The area source calculation of HEU on the front face is listed in the last column for acquisition 22. The area source value of 71 grams is in excellent agreement with the point source calculation for the front face.

Each of the calculations above yielded a value that was not transmission-corrected. Therefore we assumed in reporting our preliminary results that the value of 71 grams on the front face of the lathe represented a lower limit of content. To achieve the 50-gram limit, we recommended further decontamination.⁸

To determine the optimum places for further decontamination, we performed close-coupled and contact measurements on the front vertical surface of the lathe (Figure 3), on the chuck, ingot holder, and catch pan (Figure 4), and on the opposing force component (Figure 5). The close-coupled measurements on the vertical sides of the front of the lathe are tabulated in rows 5 through 12 of Table 1. Each of the acquisitions 5 through 12 was taken at a range of eight inches. The HEU contents were calculated assuming an area source using equation (3) with an effective field of view of 56 in² (reference 7).

[²³⁵U] = (K_a)A(measured cps) = (0.000137)(56)(cps). (3)

Acquisition 5 was obtained at a distance of eight inches from the right end of the vertical front of the lathe. Acquisitions 6 through 11 were also taken from a range of eight inches by moving the detector incrementally eight inches to the left for each successive spectrum. Acquisition 9 was taken of the chuck, and acquisition 12 was taken by viewing the holder in front of the chuck vertically from a height of eight inches. (See Figure 3.) The measured value from each of these acquisitions is listed in the last column of Table 1 in rows 5 through 12. The sum of these acquisitions indicates 25 grams holdup on these components taken together as a group.

We then obtained eighteen contact measurements in acquisitions 14 through 21 and 23 through 32. The measured values obtained from each of these contact measurements was obtained from an interactive fit of equation (4)

cpm = 1.03x10⁵m/(1 + 0.147m), (4)

which was derived empirically in reference 6. In (4), m is mass in grams of U-235 HEU residue. The close-contact measurement results are listed in the appropriate row for each acquisition in the seventh column of Table 1.

The NaI detector crystal is a cylinder of radius 13/16 inch and height 2 inches. In a close-contact configuration the detector shield is touching the surface of the item measured, and the circular base of the detector views exactly 1.41p in² of surface area of the component. Looking, for example, at the four contact spectra taken of the catch pan (Figure 4), acquisitions 14 through 17, the detector viewed a total of 5.64p in² and observed a sum of 0.76 g HEU residue. From the exact dimensions of the catch pan we obtain a total surface area of 2280 square inches. Assuming a uniform distribution of residue, this yields a total surface contamination of

[²³⁵U] = (0.76/5.64p)(2280) = 98 g.

Using very similar reasoning and calculations, the content of HEU residue on the holder under the chuck (Figure 4) can be estimated from acquisitions 18 and 19 to be

[²³⁵U] = [(0.6+1.3)/2.82p](22x35) = 165 g.

The content of HEU residue on the chuck (Figure 4) can be estimated from acquisition 21 to be

[²³⁵U] = (0.6/1.41p)(35/2)(35/2)(p) = 130 g.

Table 1. Measured 185-keV g-ray peak area and U-235 mass obtained with the
2x2 NaI detector in each configuration at 8 inches (First day)

* Point Source Value

 

Figure 3. Photograph of the A-Lathe showing measurement points 5-12

The contact estimates very likely have uncertainty near 100%. But we believe they strongly support the overall conclusion that the lathe contained gross amounts of HEU residue and demonstrated that the chuck, holder, and catch pan should be decontaminated. These assay results and conclusions were reported in reference 8.

After an initial decontamination by FDD personnel, we performed a second assay of the lathe on February 6, 2001. We do not give a thorough description of these acquisitions or calculations. The acquisitions are denoted in Figures 6 and 7. Acquisitions F1 through F4 are far-field point source counts obtained from the front of the lathe (F1) and from the two ends and back of the lathe from a distance of 48 inches. The next twelve acquisitions (C5 through C16) are close-field acquisitions obtained at a distance of 8 inches. These were taken as shown in Figures 6 and 7. In the initial decontamination, the chuck was removed from the lathe, so that acquisition C16 was actually obtained from the space formerly occupied by the chuck. The acquisitions labeled PanC1 through PanC4 were obtained vertically from above the catch pan at a distance of 8 inches.

Acquisitions C5 – C16 were intended to provide a complete view of the front face of the lathe, and acquisitions PanC1 – PanC4 were intended to provide a complete view of the catch pan. The summed content from the close-coupled measurements of the lathe front is 34.13 g, and the summed content from the close-coupled measurements of the catch pan is 14.76 grams. These two sums taken together yield 48.89 g, which is in good agreement with the sum of the four far field measurements obtained in acquisitions F1 – F4 (34.45 g). After the initial decontamination, the observed content of HEU was reduced significantly, but our uncertainty still contained 50 g within its limits. We requested further decontamination.

After the second generation assay, upon our recommendations, FDD conducted two additional decontaminations to further reduce the HEU content to below 50 grams. We performed a third and a fourth generation assay by acquiring spectra very similar to those of the second generation assay. From the data of the generation three acquisitions we estimated a content of 40 g (with an uncertainty of 100%) still remaining on the lathe. The results after the final decontamination and final assay are presented in the next section.

The interpretation of all of the holdup data acquired in each of the four assay generations is described in references 9 and 10. The interpretations of those references allowed us to report a holdup content with an uncertainty of less than 100%. In the first generation assay we observed > 75 grams of HEU residue on the lathe from the far-field measurements, and the contact measurements indicated as much as 400 grams of residue on the chuck, catch pan, and ingot holder. After an effective FDD decontamination effort, the second generation assay indicated 49 grams of residue, with most or all of it concentrated on the front face of the lathe.

Subsequent decontamination was less effective. Our estimates of the total HEU holdup dropped from 49 to 40 to 35 grams. The close-field estimates on the front face dropped from 49 to 19 to 14 grams, and the summed close-field estimates of the front face were consistently in good agreement with the far-field measurements of the front face. Decontamination efforts were never concentrated on the back and two ends of the lathe, and the other three far-field measurements of the back and two ends never changed significantly.

Since the measured values were decreasing very slowly, we concluded that each of the last six measurements of the last three assay generations provided a reasonably good determination of HEU holdup on the front face. Likewise the last three far-field assays on the back face and two ends of the lathe provided a reasonable determination of HEU holdup there. We used that technique to estimate holdup in our final analysis.^9,10

The reported value for the front face was determined by

{(summed close field + far field)_{assay 2} + (summed close field + far field)_{assay 3} +

{(18 + 49)_{assay 2} + (25 + 19)_{assay 3} + (17 + 14)_{assay 4}}/6 = (24± 13),

where the uncertainty was determined by the standard deviation of the six values. The reported value for all other faces was determined by

We reported a total content of (24± 13) + (19± 2) = (43± 13),^9,10 and this value was used in the request for deviation to manifest the HEU holdup content on the lathe.⁵

To confirm our designation of the peaks near 600 keV and 700 keV in the spectrum of Figure 2, we obtained several final spectra of the lathe using the portable high purity germanium detection system. This system is described in reference 11 and has been used extensively in HEU holdup measurements for FDD.^12-14 The HPGe spectra were acquired on May 1, 2001 in the reactor assembly area of Building 105-C. A background spectrum is shown in Figure 8, and the sample spectrum taken from the middle of the front face in the area source configuration from a range of 48 inches is shown in Figure 9.

The primary objective for the HPGe acquisitions was to confirm the diagnosis of the two peaks in the NaI spectra at about 600 KeV and 700 KeV. Note in Figure 9 that we observe peaks at 511-, 584-, 609-, 728-, 911-, 969-, and 1112-keV. Each of these is from the daughter products of decay of naturally-occurring ²³²Th. Except for the large peaks at 143-, 163-, 186- and 203-KeV, which are g-rays from the ²³⁵U HEU residue on the lathe, no other strong peaks occur in the spectrum. The high resolution spectrum of the last seven peaks confirms our diagnosis from the NaI spectra and removes any doubt that other process activity might be present as holdup on the lathe.

From the HPGe spectra we can gain another measure of HEU holdup on the lathe. From a range of 48 inches we estimate that the detector system is approximately able to view the entire front face of the lathe, so that we can rationalize use of either a point source or area source configuration in the calculations. The point-source calculation of HEU holdup is

[²³⁵U] = (K_p)(d)²(measured cps) = (2.36x10^-5)(2.54x48)²(46.17), (6)

where K_p is in units of g-sec/cm² and is taken from the HpGe detector efficiency calibration.¹¹ The measured detection rate in the 186 keV peak was 46.17 cps and yields a measure of 16.2 grams of HEU residue. This value is in excellent agreement with the value reported above.

The area source calculation of holdup from the HPGe spectrum is

[²³⁵U] = (K_a)(A)(measured cps) = (1.29x10^-5)(26900)(46.17), (7)

where K_a is in units of g-sec/cm² and is taken from the HpGe detector efficiency calibration. In reference 11 we determined that at a range of 48 inches the detection system views an effective area of 26900 cm² or 4200 in². The measured detection rate in the 186 keV peak was 46.17 and yields a measure of 16.0 grams of HEU residue. This value is also in excellent agreement with the value reported above and with that of equation (6).

3.3 Individual Assay of Lathe Residue

In order to gain a mass balance on the measured values, we assayed the residue and sweepings from the lathe that were placed in the scrap cans referenced in experimental sections 2.2. The chuck and the floor sweepings from the first and second decontamination were packaged into 55-gallon drum FD2191, and the can of HEU chips was packaged into 55-gallon drum FD2189. Both drums were shipped from C-Area to M-Area for assay on the Canberra Q² transmission-corrected g-PHA solid waste assay instrument. The drums were assayed by the direct Q² technique and by the adapted three-segment segmented gamma scanner technique. The latter technique uses a 4.41-g source of U-235 to obtain a transmission measurement for each of three vertical segments of the drum and is described in references 15 and 16.

Figure 8. HPGe Background Spectrum in 105-C

Figure 9. HPGe Spectrum of the Front Face of the Lathe

The direct Q² assay method yielded 24 g of ²³⁵U in FD2189, while the adapted technique yielded 35 g. The direct assay method yielded 45 g in FD2191. Both of these drums were very massive. FD2189 was 81 kg, and FD2191 was 187 kg. The transmission correction on each was very large. The transmission through the bottom section of FD2191 could not even be measured by using the adapted technique, therefore no measured ²³⁵U content could be reported by that technique. Because of the high densities, all of the Q² measurements have large uncertainties.

The drums were then unpacked so that some of the items could be assayed individually. We were particularly interested in the results for the individual assay of the scrap can that contained the floor sweepings and chips from the lathe decontaminations. We were also interested in the results from holdup measurements of the chuck. The individual scrap can assays are discussed in the next section.

After removal of the scrap can from drum FD2189, it was re-assayed as drum FD2189-1 using the direct Q² technique only. Though it was not repacked, drum FD2191 was also re-assayed as drum FD2191-1. In addition, we used the direct Q² technique to assay the job control material and instacoat material from the decontaminations of the lathe. These were packaged into drum FD1992, which was assayed by the direct Q² technique. The results of the direct Q² assays are listed in Table 2. Table 2 also contains results from the direct assay of three additional drums that we discuss later in this report. Uncertainties are estimated to be about 60%.

The results of Table 2 demonstrate that drum FD2191, which contains the chuck from the lathe, could be assayed with good precision to have 40 – 50 grams of ²³⁵U holdup. Drum FD2189 contained approximately 20 – 30 grams of HEU residue, which was contained entirely in the scrap can. Drum FD1992 contains approximately 10 – 20 grams of ²³⁵U contamination from the decontamination activities performed in the 105-C Decon Facility.

For drum manifest purposes, we note that drum FD2189 now contains 0.3± 0.2 g HEU, the content of drum FD2191 was reported as 48± 29 g, and the content of drum FD1992 is14± 8 g.

Table 2. Direct Q2 assay results for several drums that contained lathe
decontamination job control material and residue

The scrap can that contained the lathe residue was assayed using the 321-M transmission corrected billet assay station. The assay station was efficiency calibrated using the traditional far-field transmission-corrected configuration and using an empirical transmission correction.^17,18 Both of these techniques are described in reference 11.

The billet assay station far-field transmission-correction technique uses equation (6) with distance equals 45.5 inches, and the transmission correction uses the traditional source shine through.

[²³⁵U] = (K_p)(d)²(measured cps)(Cf) = (2.36x10^-5)(2.54x45.5)²(cps)(Cf). (6)

The transmission source was a mass of 4.41 g of U-235. The transmission-corrected data are listed in Table 3, which is an Excel spreadsheet that performs the transmission-corrected assay calculations. The unabsorbed transmission source spectrum T₀ was acquired at a distance of 74 inches and had a count rate of 5.81 cps in the ²³⁵U peak. Using equation (6) with spectrum T₀ we obtain a satisfactory QC check of the system.

[²³⁵U] = (K_p)(d)²(measured cps)(Cf) = (2.36x10^-5)(2.54x74)²(5.81)(1), (6)

= 4.84± 0.24 g.

We also performed quality control checks of the system by counting each of three sources with U-235 contents of 0.69-g, 1.01-g, and 15.66-g in the far field transmission corrected configuration. Results and uncertainties are listed in columns 10 and 11 and in columns 12 and 13 of Table 3. We obtained excellent transmission-corrected agreement for these three sources, but we note that the method fails when the sample self-absorption becomes large. The empirical results are in excellent agreement with the known values for all five of the sources shown in Table 3. We had previously set our upper limit for this technique with scrap cans at 30 g,^14,18

The spectrum acquired of scrap can W0412, which contained the HEU residue from the decontaminaton of the lathe, had a detection rate of 46.40 cps in the sample-only spectrum (W0412) and a rate of 48.54 cps in the transmission spectrum (W0412T). These data are listed in Table 3 also. From equation (6), we obtained a measured content of 24.1± 1.6 g with a transmission-correction factor of 1.65. The Deming interactive fit of spectrum W0412 yielded a content of 31.7± 3.3 g. To improve accuracy in these measurements, we requested that scrap can W0412 be repackaged into three separate cans that would have lower mass and lower transmission correction.

In summary, we originally measured > 75 g HEU on the lathe. After three decontaminations we measured approximately 40 g left on the lathe and approximately 90 g in the decontamination material recovered. This total of 130 g is well within the original estimate and closes the material balance. Due to the uncertainties in the measurements, the 40-g reported remaining might be as high as 53 g, so a deviation request for disposal over the 50 g limit was requested to be sure that the conservative bases of the WAC are maintained.

Table 3. Results of the transmission corrected far field g-PHA assay of scrap cans

We have used four techniques to conduct the holdup assay of ²³⁵U in the 321-M A process lathe at SRS. The holdup assays were conducted over a period of five months in which we performed four distinct measurements after three successive decontaminations of the lathe. In order to gain closure and to lend support to our measurements, we also conducted assay measurements of the residual HEU scrap that was removed from the lathe in the decontaminations. For the same purposes, we conducted assays of the HEU contamination that remained on the job control waste material and that remained on the individual working components as they were removed from the lathe.

Our initial far field holdup assay performed with a NaI detection system demonstrated that at least 75 g of HEU residue and contamination were on the lathe. Close-field and contact measurements indicated the value could be as high as several hundred grams. After three successive decontamination efforts by FDD operators we finally reported a total content of 43± 13 grams remaining on the lathe. This value with uncertainty was accepted with a request for a deviation to allow removal of the lathe for on-site burial. The deviation was required because the reported value plus uncertainty exceeds the criticality limit of 50 g HEU for an individual B-25 container. Follow up assay of the front face of the decontaminated lathe using a high purity germanium detection system yielded results in very good agreement with the final NaI measurements.

Our assays of the decontamination job control material, of the chuck component of the lathe, and of the HEU residue removed from the lathe were conducted using the 321-M assay station and using the 313-M Q² assay instrument. Together these items were packaged into three 55-gallon drums that we assayed using either the direct Q² technique or using the adapted three-segment technique. In these three drums we observed a summed content of 80 g HEU, for which we estimated an uncertainty of 60%.

The scrap can of HEU residue that was inside one drum was removed and assayed on the 321-M far-field transmission-corrected assay station. In our measurements we observed a content of 32± 3 g, in very good agreement with the adapted Q² measurement of 35± 13 g. Because of the fairly large content, the can was repackaged into three separate cans that were again separately measured on the assay station. In these three cans we observed a sum of 36± 2 g. These individual cans were subsequently packaged into separate 55-gallon drums that were assayed by the direct Q² technique. We observed a total of 20± 12 g in these three measurements.

For closure we have reported a total of 43± 13 g remaining on the lathe and a total of about 90± 40 g removed from the lathe in one form or another. Thus we have accounted for a total of approximately 130± 40 g of HEU. This is in very good support of our initial report of >75 g of HEU holdup on the lathe.

1. D. L. Honkonen, "Nuclear Criticality Safety Evaluation (NCSE): Enriched Uranium Removal From Building 321-M", N-NCS-G-00051, February 2000.
2. R. S. Thomason, "U-235 Holdup in Building 321-M Contamination Areas and Associated Exhaust Systems", WSRC-TR-95-0492, December 1995.
3. Deactivation Project Plan 321-M Fuel Fabrication Facility, V-PMP-M-00004, January 2000.
4. WSRC 1S Manual, Procedure 3.17, Section A.3.a, "E-Area Vaults Nuclear Safety", July 2000.
5. R. H. Holmes, "Request/Approval for Deviation", SWMD-RFD-2001-0017, April 2001.
6. R. A. Dewberry and S. R Salaymeh, "Efficiency Calibration Using HEU Standards of 2" x 2" NaI Detector", WSRC-TR-2000-00269, July 2000.
7. R. A. Dewberry, Laboratory Notebook WSRC-NB-2000-00086, pg 1-45.
8. R. A. Dewberry to George Joyner, "Lathe U-235 Assays", SRT-ADS-2001-0001, January 2001.
9. R. A. Dewberry to J. N. Hall, "Summary of Lathe Measurements", SRT-ADS-2001-0112, March 2001.
10. R. A. Dewberry and S. R Salaymeh, "Holdup Measurements in the 321-M Lathe", WSRC-TR-2001-00296, June 2001.
11. S. R Salaymeh and R. A. Dewberry, "HPGe Detector Efficiency Calibration Using HEU Standards", WSRC-TR-2000-00317, September 2000.
12. R. A. Dewberry and S. R Salaymeh, "U-235 Holdup Measurements of Mixed Waste at SRS", WSRC-TR-1999-00396, October 1999.
13. R. A. Dewberry, S. R Salaymeh and F. S. Moore "HPGe g-PHA Assay of Uranium Storage Pigs for 321-M Facility", WSRC-TR-2001-00031, May 2001.
14. S. R Salaymeh, R. A. Dewberry and V. R. Casella "HEU Holdup Measurements in 321-M FreonÔ Cart", WSRC-TR-2000-00360, September 2000.
15. S. R Salaymeh and R. A. Dewberry, "Adapting the CANBERRA Q² to Assay High Density Solid Waste From 321-M", WSRC-TR-2001-00004, January 2001.
16. S. R Salaymeh and R. A. Dewberry, "Scrap Cans Assayed in 55 Gallon Drums by Adapted Q² Technique", WSRC-TR-2001-00085, March 2001.
17. Deming Least Squares Curve Fitting for Windows, Version 1.13, Safeguards Science and Technology Group (NIS-5), Los Alamos National Laboratory.
18. S. R Salaymeh, R. A. Dewberry and V. R. Casella, "High Purity Germanium Assay of Uranium Scrap Cans Used in the 321-M Facility", WSRC-TR-2001-00084, December 2001.