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Calibrations of a tritium extraction facility

Description: A tritium extraction facility has been built for the purpose of measuring the absolute tritium concentration in neutron-irradiated lithium metal samples. Two independent calibration procedures have been used to determine what fraction, if any, of tritium is lost during the extraction process. The first procedure compares independently measured /sup 4/He and /sup 3/H concentrations from the /sup 6/Li(n,..cap alpha..)T reaction. The second procedure compared measured /sup 6/Li(n,..cap alpha..)T//sup 197/Au (n,..gamma..)/sup 198/Au thermal neutron reaction rate ratios with those obtained from Monte Carlo calculations using well-known cross sections. Both calibration methods show that within experimental errors (approx. 1.5%) no tritium is lost during the extraction process.
Date: January 1, 1983
Creator: Bretscher, M.M.; Oliver, B.M. & Farrar, H. IV
Partner: UNT Libraries Government Documents Department

Measurements and calculation of /sup 10/B(n,He) and /sup 235/U(n,f) reaction rates and a control rod mockup in ZPPR (Zero Power Plutonium Reactor)

Description: Results are reported for /sup 10/B(n,He) reaction rate measurements inside B/sub 4/C pellets in a prototypic control rod mockup in the Zero Power Plutonium Reactor. The helium accumulation fluence monitor (HAFM) technique was used, with absolute amounts of helium measured by isotope dilution mass spectrometry. Rates of /sup 235/U fission were measured in foils irradiated between B/sub 4/C pellets. Both helium production and uranium fission rates were calculated using three-dimensional nodal transport methods. Average C/E values in the control rod were 0.961 +- 0.034 for boron capture and 1.094 +- 0.008 for uranium fission based on ENDF/B version V.2 cross sections. The C/E values were nearly constant in the rod interior but changed by a few percent near the rod tip. For both reactions, the C/E values were brought closer to unity by increasing the boron capture cross sections.
Date: January 1, 1986
Creator: Brumbach, S.B.; Collins, P.J.; Grasseschi, G.L. & Oliver, B.M.
Partner: UNT Libraries Government Documents Department

Helium generation rates in isotopically tailored Fe-Cr-Ni alloys irradiated in FFTF/MOTA

Description: Three Fe-Cr-Ni alloys have been doped with 0.4% {sup 59}Ni for side-by-side irradiations of doped and undoped materials in order to determine the effects of fusion-relevant levels of helium production on microstructural development and mechanical properties. The alloys were irradiated in three successive cycles of the Materials Open Test Assembly (MOTA) located in the Fast Flux Test Facility (FFTF). Following irradiation, helium levels were measured by isotope dilution mass spectrometry. The highest level of helium achieved in doped alloys was 172 appm at 9.1 dpa for a helium(appm)-to-dpa ratio of 18.9. The overall pattern of predicted helium generation rates in doped and undoped alloys is in good agreement with the helium measurements.
Date: November 1, 1991
Creator: Greenwood, L. R.; Garner, F. A. & Oliver, B. M.
Partner: UNT Libraries Government Documents Department

Neutron dosimetry of the HFIR hydraulic facility

Description: The total, fast, and thermal neutron fluxes at five axial positions in the High Flux Isotope Reactor (HFIR) hydraulic tube have been measured using bare and/or cadmium-covered activation, fission, and helium accumulation flux monitors. The spectrum-averaged, one-group cross sections over selected energy ranges for the reactions used in the measurements were obtained using cross sections from the ENDF/B-V file, and the target region volume-integrated spectrum was calculated with DORT, a two-dimensional discrete ordinates radiation transport code. The fluxes obtained from various monitors are in good agreement. The total and fast (>l MeV) neutron fluxes vary from 1.6 {times} 10{sup 19} n/m{sup 2} {center_dot} s and 1.6 {times} 10{sup 18} n/m{sup 2} {center_dot} s, respectively at the ends (HT-1 and -9) of the facility to 4.0 {times} 10{sup 19} n/m{sup 2} {center_dot} s and 4.6 {times} 10{sup 18} n/m{sup 2} {center_dot} s, respectively, at the center (HT-5) of the facility. The thermal-to-fast (>1 MeV) flux ratio varies from about 5.4 at the center to about 6.7 at the ends of the facility. The ratio of fast flux greater than 0.1 MeV to that greater than 1 MeV is 2.0 and stays almost constant along the length of the tube.
Date: February 1, 1995
Creator: Mahmood, S.T.; Mirzadeh, S.; Farrell, K.; Pace, J.V. III & Oliver, B.M.
Partner: UNT Libraries Government Documents Department

Integral measurement of {sup 9}Be(n,2n){sup 8}Be in the {sup 9}Be(d, n) neutron spectrum

Description: {sup 4}He production has been measured, by an isotopic dilution mass spectrometry method, for the irradiation of Be-metal samples by fast neutrons from the {sup 9}Be(d,n) source reaction, corresponding to 7-MeV deuterons incident on a thick Be-metal target. The {sup 58}Ni(n,p){sup 58g+m}Co dosimetry reaction was employed as a reference standard for measurement of the neutron flux. The integral cross section for the {sup 9}Be(n,2n){sup 8}Be(2{sup 2}He) reaction was deduced by applying a correction of 9.4% to account for the {sup 9}Be(n,{alpha}){sup 6}He reaction contribution to the total {sup 4}He yield from neutrons on Be. The experimental integral reaction cross-section ratio of {sup 9}Be(n,2n)2{sup 4}He to {sup 58}Ni(n,p){sup 58g+m}Co in this spectrum was found to be 1.217, with an error of {approximately} 3.5%. This can be compared to the corresponding calculated ratio of 1.161, based on an average of results obtained by considering four distinct representations of the {sup 9}Be(d,n) neutron spectrum and ENDF/B-VI values for the reaction cross sections. The scatter of the calculated results amounts to {approximately} 0.3%. It is small because the shapes of the response functions, R(E)={phi}(E){sigma}(E), for these two reactions in this neutron spectrum are very similar. The observed C/E is 0.954. This is excellent agreement, considering the various uncertainties involved, including those for the differential cross sections from ENDF/B-VI.This particular integral measurement is sensitive to the differential reaction cross section in the range 3--6 MeV. Therefore, the results of the present investigation indicate that ENDF/B-VI represents the {sup 9}Be(n,2n)2{sup 4}He reaction differential cross section quite well in this energy range.
Date: May 1, 1993
Creator: Meadows, J. W.; Smith, D. L.; Greenwood, L. R.; Kneff, D. W. & Oliver, B. M.
Partner: UNT Libraries Government Documents Department

Drying results of K-Basin fuel element 0309M (Run 3)

Description: An N-Reactor outer fuel element that had been stored underwater in the Hanford 100 Area K-West Basin was subjected to a combination of low- and high-temperature vacuum drying treatments. These studies are part of a series of tests being conducted by Pacific Northwest National Laboratory on the drying behavior of spent nuclear fuel elements removed from both the K-West and K-East Basins. The drying test series was designed to test fuel elements that ranged from intact to severely damaged. The fuel element discussed in this report was removed from K-West canister 0309M during the second fuel selection campaign, conducted in 1996, and has remained in wet storage in the Postirradiation Testing Laboratory (PTL, 327 Building) since that time. The fuel element was broken in two pieces, with a relatively clean fracture, and the larger piece was tested. A gray/white coating was observed. This was the first test of a damaged fuel element in the furnace. K-West canisters can hold up to seven complete fuel assemblies, but, for purposes of this report, the element tested here is designated as Element 0309M. Element 0309M was subjected to drying processes based on those proposed under the Integrated Process Strategy, which included a hot drying step.
Date: July 1, 1998
Creator: Oliver, B.M.; Klinger, G.S.; Abrefah, J.; Marschman, S.C.; MacFarlan, P.J. & Ritter, G.A.
Partner: UNT Libraries Government Documents Department

Drying results of K-Basin fuel element 5744U (Run 4)

Description: The water-filled K-Basins in the Hanford 100 Area have been used to store N-Reactor spent nuclear fuel (SNF) since the 1970s. Because some leaks in the basins have been detected and some of the fuel is breached due to handling damage and corrosion, efforts are underway to remove the fuel elements from wet storage. An Integrated Process Strategy (IPS) has been developed to package, dry, transport, and store these metallic uranium fuel elements in an interim storage facility on the Hanford Site. Information required to support the development of the drying processes, and the required safety analyses, is being obtained from characterization tests conducted on fuel elements removed from the K-Basins. A series of whole element drying tests (reported in separate documents, see Section 8.0) have been conducted by Pacific Northwest National Laboratory (PNNL) on several intact and damaged fuel elements recovered from both the K-East and K-West Basins. This report documents the results of the fourth of those tests, which was conducted on an N-Reactor outer fuel element removed from K-West canister 5744U. This element (referred to as Element 5744U) was stored underwater in the K-West Basin from 1983 until 1996. Element 5744U was subjected to a combination of low- and high-temperature vacuum drying treatments that were intended to mimic, wherever possible, the fuel treatment strategies of the IPS. The system used for the drying test was the Whole Element Furnace Testing System, described in Section 2.0, located in the Postirradiation Testing Laboratory (PTL, 327 Building). The test conditions and methodologies are given in Section 3.0. Inspections of the fuel element before and after the test are provided in Section 4.0. The experimental results are provided in Section 5.0, and discussed in Section 6.0.
Date: July 1, 1998
Creator: Klinger, G.S.; Oliver, B.M.; Abrefah, J.; Marschman, S.C.; MacFarlan, P.J. & Ritter, G.A.
Partner: UNT Libraries Government Documents Department

Drying results of K-Basin fuel element 1990 (Run 1)

Description: The water-filled K-Basins in the Hanford 100-Area have been used to store N-Reactor spent nuclear fuel (SNF) since the 1970s. Because some leaks in the basins have been detected and some of the fuel is breached due to handling damage and corrosion, efforts are underway to remove the fuel elements from wet storage. An Integrated Process Strategy (IPS) has been developed to package, dry, transport, and store these metallic uranium fuels in an interim storage facility on the Hanford Site (WHC 1995). Information required to support the development of the drying processes, and the required safety analyses, is being obtained from characterization tests conducted on fuel elements removed from the K-Basins. A series of whole element drying tests (reported in separate documents, see Section 8.0) have been conducted by Pacific Northwest National Laboratory (PNNL) on several intact and damaged fuel elements recovered from both the K-East and K-West Basins. This report documents the results of the first of those tests (Run 1), which was conducted on an N-Reactor inner fuel element (1990) that had been stored underwater in the K-West Basin (see Section 2.0). This fuel element was subjected to a combination of low- and high-temperature vacuum drying treatments that were intended to mimic, wherever possible, the fuel treatment strategies of the IPS. The testing was conducted in the Whole Element Furnace Testing System, described in Section 3.0, located in the Postirradiation Testing Laboratory (PTL, 327 Building). The test conditions and methodology are given in Section 4.0, and the experimental results provided in Section 5.0. These results are further discussed in Section 6.0.
Date: June 1, 1998
Creator: Marschman, S.C.; Abrefah, J.; Klinger, G.S.; Oliver, B.M.; MacFarlan, P.J. & Ritter, G.A.
Partner: UNT Libraries Government Documents Department

Spent fuel drying system test results (second dry-run)

Description: The water-filled K-Basins in the Hanford 100 Area have been used to store N-Reactor spent nuclear fuel (SNF) since the 1970s. Because some leaks have been detected in the basins and some of the fuel is breached due to handling damage and corrosion, efforts are underway to remove the fuel elements from wet storage. An Integrated Process Strategy (IPS) has been developed to package, dry, transport, and store these metallic uranium fuel elements in an interim storage facility on the Hanford Site (WHC 1995). Information required to support the development of the drying processes, and the required safety analyses, is being obtained from characterization tests conducted on fuel elements removed from the K-Basins. A series of whole element drying tests (reported in separate documents, see Section 7.0) have been conducted by Pacific Northwest National Laboratory (PNNL) on several intact and damaged fuel elements recovered from both the K-East and K-West Basins. This report documents the results of the second dry-run test, which was conducted without a fuel element. With the concurrence of project management, the test protocol for this run, and subsequent drying test runs, was modified. These modifications were made to allow for improved data correlation with drying procedures proposed under the IPS. Details of these modifications are discussed in Section 3.0.
Date: July 1, 1998
Creator: Klinger, G.S.; Oliver, B.M.; Abrefah, J.; Marschman, S.C.; MacFarlan, P.J. & Ritter, G.A.
Partner: UNT Libraries Government Documents Department

Spent fuel drying system test results (first dry-run)

Description: The water-filled K-Basins in the Hanford 100 Area have been used to store N-Reactor spent nuclear fuel (SNF) since the 1970s. Because some leaks in the basin have been detected and some of the fuel is breached due to handling damage and corrosion, efforts are underway to remove the fuel elements from wet storage. An Integrated Process Strategy (IPS) has been developed to package, dry, transport, and store these metallic uranium fuel elements in an interim storage facility on the Hanford Site. Information required to support the development of the drying processes, and the required safety analyses, is being obtained from characterization tests conducted on fuel elements removed from the K-Basins. A series of whole element drying tests (reported in separate documents, see Section 7.0) have been conducted by Pacific Northwest National Laboratory (PNNL) on several intact and damaged fuel elements recovered from both the K-East and K-West Basins. This report documents the results of the first dry-run test, which was conducted without a fuel element. The empty test apparatus was subjected to a combination of low- and high-temperature vacuum drying treatments that were intended to mimic, wherever possible, the fuel treatment strategies of the IPS. The data from this dry-run test can serve as a baseline for the first two fuel element tests, 1990 (Run 1) and 3128W (Run 2). The purpose of this dry-run was to establish the background levels of hydrogen in the system, and the hydrogen generation and release characteristics attributable to the test system without a fuel element present. This test also serves to establish the background levels of water in the system and the water release characteristics. The system used for the drying test series was the Whole Element Furnace Testing System, described in Section 2.0, which is located in the Postirradiation Testing Laboratory ...
Date: July 1, 1998
Creator: Klinger, G.S.; Oliver, B.M.; Abrefah, J.; Marschman, S.C.; MacFarlan, P.J. & Ritter, G.A.
Partner: UNT Libraries Government Documents Department

Drying results of K-Basin fuel element 1164M (run 6)

Description: The water-filled K-Basins in the Hanford 100 Area have been used to store N-Reactor spent nuclear fuel (SNF) since the 1970s. Because some leaks in the basin have been detected and some of the fuel is breached due to handling damage and corrosion, efforts are underway to remove the fuel elements from wet storage. An Integrated Process Strategy (IPS) has been developed to package, dry, transport, and store these metallic uranium fuel elements in an interim storage facility on the Hanford site (WHC 1995). Information required to support the development of the drying processes, and the required safety analyses, is being obtained from characterization tests conducted on fuel elements removed from the K-Basins. A series of whole element drying tests (reported in separate documents, see Section 8.0) have been conducted by Pacific Northwest National Laboratory (PNNL) on several intact and damaged fuel elements recovered from both the K-East and K-West Basins. This report documents the results of the sixth of those tests, which was conducted on an N-Reactor outer fuel element removed from K-West canister 1164 M. This element (referred to as Element 1164M) was stored underwater in the K-West Basin from 1983 until 1996. Element 1164M was subjected to a combination of low- and high-temperature vacuum drying treatments that were intended to mimic, wherever possible, the fuel treatment strategies of the IPS. The system used for the drying test was the Whole Element Furnace Testing System, described in Section 2.0, located in the Postirradiation Testing laboratory (PTL, 327 Building). The test conditions and methodologies are given in Section 3.0. Inspections of the fuel element before and after the test are provided in Section 4.0. The experimental results are provided in Section 5.0, and discussed in Section 6.0.
Date: August 1, 1998
Creator: Oliver, B.M.; Klinger, G.S.; Abrefah, J.; Marschman, S.C.; MacFarlan, P.J. & Ritter, G.A.
Partner: UNT Libraries Government Documents Department

Drying Results of K-Basin Fuel Element 6603M (Rune 5)

Description: The water-filled K-Basins in the Hanford 100 Area have been used to store N-Reactor spent nuclear fuel (SNF) since the 1970s. An Integrated Process Strategy (IPS) has been developed to package, dry, transport, and store these metallic uranium spent nuclear fuels in an interim storage facility on the Hanford Site (WHC 1995). Information required to support the development of the drying processes, and the required safety analyses, is being obtained from characterization tests conducted on fuel elements removed from the K-Basins. A series of drying tests (reported in separate documents, see Section 8.0) have been conducted by Pacific Northwest National Laboratory (PNNL) on several intact and damaged fuel elements recovered from both the K-East and K-West Basins. This report documents the results of the fifth of those tests conducted on an N-Reactor outer fuel element (6603M) which had been stored underwater in the Hanford 100 Area K-West basin from 1983 until 1996. This fuel element was subjected to a combination of low- and high-temperature vacuum drying treatments which were intended to mimic, wherever possible, the fuel treatment strategies of the IPS. The system used for the drying test was the Whole Element Furnace Testing System, described in Section 2.0. The test conditions and methodologies are given in Section 3.0. Inspections on the fuel element before and after the test are provided in Section 4.0. The experimental results are provided in Section 5.0. Discussion of the results is given in Section 6.0.
Date: September 24, 1999
Creator: Oliver, B.M.; Ritter, G.A.; Klinger, G.S.; Abrefah, J.; Greenwood, L.R.; MacFarlan, P.J. et al.
Partner: UNT Libraries Government Documents Department

Drying Results of K-Basin Fuel Element 6513U (Run 8)

Description: The water-filled K-Basins in the Hanford 100 Area have been used to store N-Reactor spent nuclear fuel (SNF) since the 1970s. Because some leaks in the basin have been detected and some of the fuel is breached due to handling damage and corrosion, efforts are underway to remove the fuel elements from wet storage. An Integrated Process Strategy (IPS) has been developed to package, dry, transport, and store these metallic uranium fuel elements in an interim storage facility on the Hanford Site (WHC 1995). Information required to support the development of the drying processes, and the required safety analyses, is being obtained from characterization tests conducted on fuel elements removed from the K-Basins. A series of whole element drying tests (reported in separate documents, see Section 8.0) have been conducted by Pacific Northwest National Laboratory (PNNL)on several intact and damaged fuel elements recovered from both the K-East and K-West Basins. This report documents the results of the eighth of those tests, which was conducted on an N-Reactor outer fuel element removed from K-West canister 6513U. This element (referred to as Element 6513U) was stored underwater in the K-West Basin from 1983 until 1996. Element 6513U was subjected to a combination of low- and high-temperature vacuum drying treatments that were intended to mimic, wherever possible, the fuel treatment strategies of the IPS. The system used for the drying test was the Whole Element Furnace Testing System, described in Section 2.0, located in the Postirradiation Testing Laboratory (PTL, 327 Building). The test conditions and methodologies are given in Section 3.0. Inspections of the fuel element before and after the test are provided in Section 4.0. The experimental results are provided in Section 5.0 and discussed in Section 6.0.
Date: August 11, 1999
Creator: Oliver, B. M.; Klinger, G. S.; Abrefah, J.; Marschman, S. C.; MacFarlan, P. J. & Ritter, G. A.
Partner: UNT Libraries Government Documents Department

Drying Results of K-Basin Fuel Element 2660M (Run 7)

Description: The water-filled K-Basins in the Hanford 100 Area have been used to store N-Reactor spent nuclear fuel (SNF) since the 1970s. Because some leaks in the basin have been detected and some of the fuel is breached due to handling damage and corrosion, efforts are underway to remove the fuel elements from wet storage. An Integrated Process Strategy (IPS) has been developed to package, dry, transport, and store these metallic uranium fuel elements in an interim storage facility on the Hanford Site (WHC 1995). Information required to support the development of the drying processes, and the required safety analyses, is being obtained from characterization tests conducted on fuel elements removed from the K-Basins. A series of whole element drying tests (reported in separate documents, see Section 8.0) have been conducted by Pacific Northwest National Laboratory (PNNL) on several intact and damaged fuel elements recovered from both the K-East and K-West Basins. This report documents the results of the seventh of those tests, which was conducted on an N-Reactor outer fuel element removed from K-West canister 2660M. This element (referred to as Element 2660M) was stored underwater in the K-West Basin from 1983 until 1996. Element 2660M was subjected to a combination of low- and high-temperature vacuum drying treatments that were intended to mimic, wherever possible, the fuel treatment strategies of the IPS. The system used for the drying test was the Whole Element Furnace Testing System, described in Section 2.0, located in the Postirradiation Testing Laboratory (PTL, 327 Building). The test conditions and methodologies are given in Section 3.0. Inspections of the fuel element before and after the test are provided in Section 4.0. The experimental results are provided in Section 5.0, and discussed in Section 6.0.
Date: July 26, 1999
Creator: Oliver, B.M.; Klinger, G.S.; Abrefah, J.; Marschman, S.C.; MacFarlan, P.J. & Ritter, G.A.
Partner: UNT Libraries Government Documents Department

The influence of helium on mechanical properties of model austenitic alloys, determined using sup 59 Ni isotopic tailoring and fast reactor irradiation

Description: The objective of this effort is to study the separate and synergistic effects of helium and other important variables on the evolution of microstructure and macroscopic properties during irradiation of structural metals. The alloys employed in this study were nominally Fe-15Cr-25Ni, Fe-15Cr-25Ni-0.04P and Fe-15Cr-45Ni (wt %) in both the cold worked and annealed conditions. Tensile testing and microscopy continue on specimens removed from the first, second and third discharges of the {sup 59}Ni isotopic doping experiment. The results to date indicate that helium/dpa ratios typical of fusion reactors (4 to 19 appm/dpa) do not lead to significant changes in the yield strength of model Fe-Cr-Ni alloys. Measurements of helium generated in undoped specimens from the second and third discharges show that the helium/dpa ratio increases during irradiation in FFTF due to the production of {sup 59}Ni. In specimens doped with {sup 59}Ni prior to irradiation, the helium/dpa ratio can increase, decrease or remain the same during the second irradiation interval. This behavior occurs because the cross sections for the production and burnout of {sup 59}Ni are very sensitive to core location and the nature of neighboring components. 14 refs., 5 figs., 3 tabs.
Date: November 1, 1990
Creator: Hamilton, M.L.; Garner, F.A. (Pacific Northwest Lab., Richland, WA (USA)) & Oliver, B.M. (Rockwell International Corp., Canoga Park, CA (USA))
Partner: UNT Libraries Government Documents Department

Helium measurements for the MFE-4 spectral tailoring experiment

Description: Measurements of helium concentration have been made on Fe-15.1Cr-34.5Ni specimens irradiated at 330, 400, 500 and 600{degree}C after irradiation in ORR to displacement levels ranging from 12.6 to 13.8 dpa. The measurements compare well to previously calculated values, being 4 to 8% lower. Minor differences in helium content were also observed between specimens from capsules that were assumed to have possessed identical spectral environments. 6 refs., 1 fig., 2 tabs.
Date: November 1, 1990
Creator: Garner, F.A. (Pacific Northwest Lab., Richland, WA (USA)) & Oliver, B.M. (Rockwell International Corp., Canoga Park, CA (USA))
Partner: UNT Libraries Government Documents Department

Stepped-anneal and total helium/hydrogen measurements in high-energy proton-irradiated tungsten

Description: To provide structural material design data for the Accelerator Production of Tritium (APT) project, a 1 mA, 800 MeV proton beam at the Los Alamos Neutron Science Center (LANSCE) was used to irradiate a large number of metal samples, including a tungsten target similar to that being considered as the neutron source for the tritium production. The maximum proton fluence to the tungsten target was {approximately} 10{sup 21} protons/cm{sup 2}. An unavoidable byproduct of spallation reactions is the formation of large amounts of hydrogen and helium. Postulated accident scenarios for APT involving the use of tungsten rods clad with Alloy 718, raise concerns as to the amount and rate of release of these gases due to temperatures increases from afterheat accumulation, with the major concern being pressurizing and possibly failure of the cladding. To address these issues, portions of the LANSCE tungsten rods were subjected to temperature histories calculated as likely to occur, and the time-dependent evolution of helium and hydrogen gases was measured. Stepped-anneal and total helium/hydrogen measurements were conducted on multiple samples of the tungsten material. Helium measurements were conducted at Pacific Northwest National Laboratory (PNNL) using a high-sensitivity magnetic-sector isotope-dilution helium analysis system. Stepped-anneal measurements were conducted at temperatures from {approximately} 25 C to {approximately} 1,600 C in {approximately} 100 C steps. Total helium measurements were conducted by rapid vaporization after completion of the stepped-anneal process, and are compared with Monte Carlo calculations performed at Los Alamos National Laboratory (LANL) using the LAHET code system. Hydrogen measurements were conducted between {approximately} 750 C and {approximately} 1,200 C using a high-temperature furnace that had been extensively modified for the application. Hydrogen detection was accomplished by periodic sampling of the furnace gas using a separate quadrupole analyzer. Hydrogen measurements are also compared with LANL calculations.
Date: December 31, 1998
Creator: Oliver, B.M.; Hamilton, M.L.; Garner, F.A.; Sommer, W.F.; Maloy, S.A. & Ferguson, P.D.
Partner: UNT Libraries Government Documents Department

Drying results of K-Basin fuel element 3128W (run 2)

Description: An N-Reactor outer fuel element that had been stored underwater in the Hanford 100 Area K-East Basin was subjected to a combination of low- and high-temperature vacuum drying treatments. These studies are part of a series of tests being conducted by Pacific Northwest National Laboratory on the drying behavior of N-Reactor spent nuclear fuel elements removed from both the K-West and K-East Basins. The drying test series was designed to test fuel elements that ranged from intact to severely damaged. The fuel element discussed in this report was removed from an open K-East canister (3128W) during the first fuel selection campaign conducted in 1995, and has remained in wet storage in the Postirradiation Testing Laboratory (PTL, 327 Building) since that time. Although it was judged to be breached during in-basin (i.e., K-Basin) examinations, visual inspection of this fuel element in the hot cell indicated that it was likely intact. Some scratches on the coating covering the cladding were identified before the furnace test. The drying test was conducted in the Whole Element Furnace Testing System located in G-Cell within the PTL. This test system is composed of three basic systems: the in-cell furnace equipment, the system gas loop, and the analytical instrument package. Element 3128W was subjected to the drying processes based on those proposed under the Integrated Process Strategy, which included a hot drying step. Results of the Pressure Rise and Gas Evolution Tests suggest that most of the free water in the system was released during the extended CVD cycle (68 hr versus 8 hr for the first run). An additional {approximately}0.34 g of water was released during the subsequent HVD phase, characterized by multiple water release peaks, with a principle peak at {approximately}180 C. This additional water is attributed to decomposition of a uranium hydrate (UO{sub 4}{center_dot}4H{sub ...
Date: July 1, 1998
Creator: Abrefah, J.; Klinger, G.S.; Oliver, B.M.; Marshman, S.C.; MacFarlan, P.J.; Ritter, G.A. et al.
Partner: UNT Libraries Government Documents Department

Helium generation rates in isotopically tailored Fe-Cr-Ni alloys irradiated in FFTF/MOTA

Description: Three Fe-Cr-Ni alloys have been doped with 0.4% {sup 59}Ni for side-by-side irradiations of doped and undoped materials in order to determine the effects of fusion-relevant levels of helium production on microstructural development and mechanical properties. The alloys were irradiated in three successive cycles of the Materials Open Test Assembly (MOTA) located in the Fast Flux Test Facility (FFTF). Following irradiation, helium levels were measured by isotope dilution mass spectrometry. The highest level of helium achieved in doped alloys was 172 appm at 9.1 dpa for a helium(appm)-to-dpa ratio of 18.9. The overall pattern of predicted helium generation rates in doped and undoped alloys is in good agreement with the helium measurements.
Date: November 1, 1991
Creator: Greenwood, L.R.; Garner, F.A. (Pacific Northwest Lab., Richland, WA (United States)) & Oliver, B.M. (Rockwell International Corp., Canoga Park, CA (United States). Rocketdyne Div.)
Partner: UNT Libraries Government Documents Department

Release criteria and pathway analysis for radiological remediation

Description: Site-specific activity concentrations were derived for soils contaminated with mixed fission products (MFP), or uranium-processing residues, using the Department of Energy (DOE) pathway analysis computer code RESRAD at four different sites. The concentrations and other radiological parameters, such as limits on background-subtracted gamma exposure rate were used as the basis to arrive at release criteria for two of the sites. Valid statistical parameters, calculated for the distribution of radiological data obtained from site surveys, were then compared with the criteria to determine releasability or need for further decontamination. For the other two sites, RESRAD has been used as a preremediation planning tool to derive residual material guidelines for uranium. 11 refs., 4 figs., 3 tabs.
Date: January 1, 1991
Creator: Subbaraman, G.; Tuttle, R.J.; Oliver, B.M. (Rockwell International Corp., Canoga Park, CA (United States). Rocketdyne Div.) & Devgun, J.S. (Argonne National Lab., IL (United States))
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Integral measurement of [sup 9]Be(n,2n)[sup 8]Be in the [sup 9]Be(d, n) neutron spectrum

Description: [sup 4]He production has been measured, by an isotopic dilution mass spectrometry method, for the irradiation of Be-metal samples by fast neutrons from the [sup 9]Be(d,n) source reaction, corresponding to 7-MeV deuterons incident on a thick Be-metal target. The [sup 58]Ni(n,p)[sup 58g+m]Co dosimetry reaction was employed as a reference standard for measurement of the neutron flux. The integral cross section for the [sup 9]Be(n,2n)[sup 8]Be(2[sup 2]He) reaction was deduced by applying a correction of 9.4% to account for the [sup 9]Be(n,[alpha])[sup 6]He reaction contribution to the total [sup 4]He yield from neutrons on Be. The experimental integral reaction cross-section ratio of [sup 9]Be(n,2n)2[sup 4]He to [sup 58]Ni(n,p)[sup 58g+m]Co in this spectrum was found to be 1.217, with an error of [approximately] 3.5%. This can be compared to the corresponding calculated ratio of 1.161, based on an average of results obtained by considering four distinct representations of the [sup 9]Be(d,n) neutron spectrum and ENDF/B-VI values for the reaction cross sections. The scatter of the calculated results amounts to [approximately] 0.3%. It is small because the shapes of the response functions, R(E)=[phi](E)[sigma](E), for these two reactions in this neutron spectrum are very similar. The observed C/E is 0.954. This is excellent agreement, considering the various uncertainties involved, including those for the differential cross sections from ENDF/B-VI.This particular integral measurement is sensitive to the differential reaction cross section in the range 3--6 MeV. Therefore, the results of the present investigation indicate that ENDF/B-VI represents the [sup 9]Be(n,2n)2[sup 4]He reaction differential cross section quite well in this energy range.
Date: January 1, 1993
Creator: Meadows, J.W.; Smith, D.L.; Greenwood, L.R. (Argonne National Lab., IL (United States)); Kneff, D.W. & Oliver, B.M. (Rockwell International Corp., Canoga Park, CA (United States). Rocketdyne Div.)
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