Experimental Drifts of Juvenile Chinook Salmon Through Effluent Discharges at Hanford in 1968 (open access)

Experimental Drifts of Juvenile Chinook Salmon Through Effluent Discharges at Hanford in 1968

Young chinook salmon held in live boxes were drifted through Hanford reactor discharges in the central Columbia River, with the objective of evaluating the affect of heated effluents on fish survival. No significant mortalities of fish were recorded from 12 drifts during the spring (March--April) when base river temperatures were low, ranging from 4 to 7.6 C. Some mortalities occurred, however, in 3 of 24 drifts conducted in late summer (August--September) when base river temperatures extended from 17 to 19.6 C. None of the mortalities resulted from passage through midstream discharge plumes, which were characterized by relatively moderate temperature increase and short duration of exposure to maximum temperatures. Mortalities occurred only when fish were drifted along the south bank of the river through areas receiving heated water via intragravel seepage from shoreline retention basins and experimental subsurface disposal of reactor effluents. The shoreline areas were characterized by impeded river flow, which restricted horizontal and vertical mixing and prolonged the exposure of drifted fish to excessively warm temperatures. The extent of thermal shock sufficient to cause death in the field is primarily an integrated function of temperature increase and exposure duration, as has been demonstrated in laboratory experiments. The numerous possible …
Date: September 24, 1969
Creator: Becker, C. D. & Coutant, C. C.
Object Type: Report
System: The UNT Digital Library
Design and Fabrication of Prototype Primary Nak Loop Valve Sets. Folder 2: Business Management and Costs (open access)

Design and Fabrication of Prototype Primary Nak Loop Valve Sets. Folder 2: Business Management and Costs

This proposal is submitted in response to Request for Proposal No. 438468, dated 27 May 1969, from the Power Procurement Section of the NASA Lewis Research Center, to design, fabricate and test Primary NaK Loop (PNL) valves for use in ground testing of the SNAP-8 Power Conversion System.
Date: June 24, 1969
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Compact thermoelectric converter. Phase II-C. Quarterly progress report, 1 January 1969--31 March 1969 (open access)

Compact thermoelectric converter. Phase II-C. Quarterly progress report, 1 January 1969--31 March 1969

None
Date: April 24, 1969
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Thermal cycle, shock, acceleration and vibration testing of a BeO reflector specimen, part No. EX-N69626085 (open access)

Thermal cycle, shock, acceleration and vibration testing of a BeO reflector specimen, part No. EX-N69626085

None
Date: April 24, 1969
Creator: Welch, F. H.
Object Type: Report
System: The UNT Digital Library
Carbon-14 extraction from reactor gas, Progress report. Production test authorization {number_sign}124 (open access)

Carbon-14 extraction from reactor gas, Progress report. Production test authorization {number_sign}124

Carbon-14 is by far the most popular of the labeled isotopes because of its adaptability to so many chemical compounds and its relatively harmless characteristic beta radiation. Because the inert gas atmosphere contains up to 30% nitrogen, carbon-14 is generated within the K Reactors by the conversion of nitrogen-14, and if not immediately oxidized, carbon-14 may remain in the reactor core for some time. It is eventually oxidized and escapes when the outward gas leakage from the reactor is vented to the stack. Production Test 124 was authorized to determine if carbon-14 could be extracted from the K gas as a profitable by-product. It was concluded that as much as 500--600 curies per year of carbon-14 could be recovered if both K Reactors were provided with relatively simple extraction facilities. This is about twice the amount of this product for which there is a current market at the present price level of approximately $3,000/curie. The grade (as specific activity) of the product recovered in the production test was low -- ranging from 3 to 26 millicuries per mol. Substantial upgrading (perhaps by a factor of 10X to 100X) is possible by skimming techniques and reduced oxidation of normal carbon at …
Date: January 24, 1969
Creator: Cooke, J. P.
Object Type: Report
System: The UNT Digital Library
Status of irradiations performed by testing and irradiation services for BNW as of October 13, 1968 (open access)

Status of irradiations performed by testing and irradiation services for BNW as of October 13, 1968

This report itemizes the irradiations performed by Testing and Irradiation Services for Battelle-Northwest. It lists the material being irradiated, awaiting disposition and material shipped during the report period.
Date: October 24, 1968
Creator: Barker, L. V.
Object Type: Report
System: The UNT Digital Library
Decays of neutral pseudoscalar mesons into lepton pairs (open access)

Decays of neutral pseudoscalar mesons into lepton pairs

The authors calculate the branching ratio {Lambda}(P {yields} {ell}{sup +}{ell}{sup -})/{Lambda}(P {yields} {gamma}{gamma}) to lowest contributing order in quantum electrodynamics, with a vector meson model for the pseudoscalar meson form factor. They treat the processes {eta} {yields} {mu}{sup +}{mu}{sup -}; {eta} {yields} e{sup +}e{sup -}; K{sub 2}{sup 0} {yields} {mu}{sup +}{mu}{sup -}; K{sub 2}{sup 0} {yields} e{sup +}e{sup -}; {pi}{sup 0} {yields} e{sup +}e{sup -}. Results are compared with those of previous calculations.
Date: September 24, 1968
Creator: Quigg, C. & Jackson, J. D.
Object Type: Report
System: The UNT Digital Library
Electron microprobe analysis of irradiated S8ER cladding (open access)

Electron microprobe analysis of irradiated S8ER cladding

Extensive precipitation was observed in S8ER cladding following irradiation. Electron microprobe analysis was proposed as a means to identify these precipitates. Subsequently, the electron microprobe was successfully used for qualitative analysis of unirradiated and irradiated S8ER cladding. The unirradiated, thermally aged control specimen analyzed showed two major precipitates. One, a randomly distributed intergranular phase, contained Ti, Mo, Fe, Cr and Ni and a second, a randomly distributed intragranular phase, contained Si, Mo, Fe, Cr and Ni. The irradiated specimen analyzed showed the same precipitates. The phase containing Ti, Mo, Fe, Cr and Ni was also randomly distributed intergranularly. The phase containing Si, Mo, Fe, Cr and Ni was in the grain boundaries, and preferentially segregated to the outer and inner diameter.
Date: August 24, 1967
Creator: Krupp, W.E. & Cooper, L.
Object Type: Report
System: The UNT Digital Library
SPEAR team report, NEPN-1 (open access)

SPEAR team report, NEPN-1

None
Date: June 24, 1967
Creator: unknown
Object Type: Report
System: The UNT Digital Library
K Reactor low alum feed test (open access)

K Reactor low alum feed test

The production reactors operated by Douglas United Nuclear, Inc., use treated Columbia River water as the coolant on a once through basis. Thus, radionuclides formed largely by the neutron activation of river salts are discharged to the river. One method of reducing the quality of radionuclides in the effluent is to increase the efficiency of parent isotope removal during the water treatment process. Prior to 1961 the water treatment process for preparing reactor coolant had been improved to the point that reactor quality coolant could be produced using an average alum flocculent feed rate of 6 ppM. Laboratory experiments carried out in 1959 and 1960 demonstrated that a markedly increased removal of parent isotopes resulted when alum feed rates in the neighborhood of 20 ppM were used. The results were confirmed by two half-plant tests of short duration in July, 1961, all water treatment plants began to use alum at a somewhat arbitrarily selected rate of 18 ppm. The practice Continues to date at all plants except at the K Reactors. The K Reactor alum feed has been limited to a nominal 15 ppM because of the high filtered water requirements. The use of the high alum feed rate did …
Date: May 24, 1967
Creator: Geier, R. G.
Object Type: Report
System: The UNT Digital Library
Functional design description and test summary of the SNAP 8 Development Reactor Mockup-1 (open access)

Functional design description and test summary of the SNAP 8 Development Reactor Mockup-1

None
Date: February 24, 1967
Creator: Kurzeka, W. J.
Object Type: Report
System: The UNT Digital Library
Test report for shock/vibration loads on test car-T7 with a dummy reactor (open access)

Test report for shock/vibration loads on test car-T7 with a dummy reactor

None
Date: February 24, 1967
Creator: Smith, T.W.
Object Type: Report
System: The UNT Digital Library
Experimental design for the preliminary study of geochemical processes (open access)

Experimental design for the preliminary study of geochemical processes

An example of the use of a simple fuctorial design to study the distribution of /sup 134/Cs and/sup 85/Sr between a soil column and solution is reported. In this design, two concentration levels of each of four factors (NaNO/ sub 3/, HNO/sub 3/, KNO/sub 3/, and Ca(NO/sub 3//sub 2/) were combined in all possible combiuations to give a total of 24 combinations. In the case of /sup 134/Cs removal, all of the independent variables were significant over their respective concentration ranges, while with the removal of /sup 85/Sr, none of the independent variables was statistically significant. Extending the concentration range of NaNO/sub 3/ caused the NaNO/sub 3/ effect total to become statistically significant at the 5% t-test level in its effects on /sup 85/Sr removal. A fractioral factorial design was used to study the removal of Sr from solutions into an apatite during a chemical reaction between phosphate ion and calcite. The Yates analysis of the Sr removal data is tabulated. It is noted that even at a t-test level of 1%, calcite surface area, influent solution pH. and system temperaturesolution pH interaction are statistically significant. The two-level factorial design yields no direct indication of the Sr removal mechanism but …
Date: March 24, 1966
Creator: Ames, L.L. Jr. & Hajek, B.F.
Object Type: Report
System: The UNT Digital Library
REACTOR DEVELOPMENT PROGRAM PROGRESS REPORT, JANUARY 1966 (open access)

REACTOR DEVELOPMENT PROGRAM PROGRESS REPORT, JANUARY 1966

None
Date: February 24, 1966
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Douglas United Nuclear, Inc. production inventory and manufacturing statement December 31, 1965 and FY to date (open access)

Douglas United Nuclear, Inc. production inventory and manufacturing statement December 31, 1965 and FY to date

None
Date: January 24, 1966
Creator: Bombino, J. J.
Object Type: Report
System: The UNT Digital Library
K Reactor uncooled HCR: Equilibrium temperature study (open access)

K Reactor uncooled HCR: Equilibrium temperature study

Temperature calculations were made on a proposed design of an uncooled horizonal control rod (HCR) for the K Reactors. The calculations were performed with the aid of a FORTRAN coded heat transfer program for the UNIVAC 1107. The results of the calculations indicate that such a control rod is feasible for.4400 Mw and 5000 Mw operation provided certain precautions are taken. These precautions include assuring good contact between the rod and the graphite in the high flux regions and Providing reasonable contact between the graphite stack and the graphite slider plates that will be placed in the bottom of the rod channels prior to rod insertion and use.
Date: January 24, 1966
Creator: Agar, J. D.
Object Type: Report
System: The UNT Digital Library
Kamchatka geothermal resources development: Problems and perspectives (open access)

Kamchatka geothermal resources development: Problems and perspectives

There are four long-term exploited geothermal fields in Kamchatka: one steam-water field Pauzhetka (south of Kamchatka peninsula) and three hot water fields: Paratunka (near by town of Petropavlovsk-Kamchatsky) and Esso and Anavgay (center of peninsula). Pauzhetka and Paratunka fields are exploited during almost 28 years. Esso and Anavgay fields are exploited during 25 years. In Pauzhetka 11 MWe geothermal power plant work and on the other fields thermal energy of hot water is directly used. Kamchatka region satisfies energetic demands mainly by organic imported fuels. At the same time electricity produced by geothermal fluids constitutes less than 2 per cent of total region electricity production, and thermal energy produced by geothermal fluids constitutes less than 3 per cent of total region thermal energy production. The main reasons of small geothermal portion in the energy production balance of Kamchatka are briefly discussed. The geothermal development reserves and perspectives of geothermal energy use increase in Kamchatka are outlined.
Date: January 24, 1966
Creator: Pashkevich, Roman I.
Object Type: Article
System: The UNT Digital Library
SOURCE OF HIGH ENERGY PARTICLES FROM AN INTERNAL TARGET IN THE AGS (open access)

SOURCE OF HIGH ENERGY PARTICLES FROM AN INTERNAL TARGET IN THE AGS

None
Date: January 24, 1966
Creator: Moore, W.H.
Object Type: Report
System: The UNT Digital Library
Processing of Counting Data (open access)

Processing of Counting Data

None
Date: September 24, 1965
Creator: Stevenson, P. C.
Object Type: Report
System: The UNT Digital Library
Operation Roller Coaster. Project Officers Report - Project 5.2/5.3b. Radiobiological, Radiochemical, and Physiochemical Analyses (open access)

Operation Roller Coaster. Project Officers Report - Project 5.2/5.3b. Radiobiological, Radiochemical, and Physiochemical Analyses

None
Date: August 24, 1965
Creator: Wessman, R. A.
Object Type: Report
System: The UNT Digital Library
Properties of Plutonium Dioxide (open access)

Properties of Plutonium Dioxide

None
Date: August 24, 1965
Creator: Moseley, J. D. & Wing, R. O.
Object Type: Report
System: The UNT Digital Library
REACTOR DEVELOPMENT PROGRAM PROGRESS REPORT, JULY 1965 (open access)

REACTOR DEVELOPMENT PROGRAM PROGRESS REPORT, JULY 1965

None
Date: August 24, 1965
Creator: unknown
Object Type: Report
System: The UNT Digital Library
DATA SET FOR LOW-SPEED REMOTE TERMINALS (open access)

DATA SET FOR LOW-SPEED REMOTE TERMINALS

Data transmission over telephone lines involves the acceptance of serialized binary data, modulation of the data to a signal suitable to the bandwidth of the telephone. channel, transmission of the signal over the line, reception at the receiving end and demodulation of the signal to reproduce the original binary data. One typical application of data communication is between a low-speed terminal and a computer. In such a case, full-duplex operation is often desirable (i,e., transmission of information on the line in both directions simultaneously). The data set described in this report operates full-duplex and provides for channelization of the telephone line for the simultaneous use of several data sets. The data set can either be coupled to leased telephone lines or acoustically coupled to any telephone.
Date: June 24, 1965
Creator: Crockett, E D
Object Type: Report
System: The UNT Digital Library
PLUTONIUM PARTICLE-INDUCED NEOPLASIA OF THE CANINE LUNG. I. CLINICAL AND GROSS PATHOLOGY (open access)

PLUTONIUM PARTICLE-INDUCED NEOPLASIA OF THE CANINE LUNG. I. CLINICAL AND GROSS PATHOLOGY

None
Date: June 24, 1965
Creator: Park, J.F.; Clarke, W.J. & Bair, W.J.
Object Type: Report
System: The UNT Digital Library