WorldCat Identities

National Reactor Testing Station, Idaho (U.S.)

Overview
Works: 441 works in 821 publications in 1 language and 6,028 library holdings
Genres: Periodicals  Handbooks and manuals 
Classifications: HE199.5.R3,
Publication Timeline
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Most widely held works about National Reactor Testing Station, Idaho (U.S.)
 
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Most widely held works by National Reactor Testing Station, Idaho (U.S.)
Chemical processing technology quarterly progress report( )

in English and held by 24 WorldCat member libraries worldwide

Shipping of radioactive material at the National Reactor Testing Station by R.V Batie( Book )

2 editions published between 1959 and 1960 in English and held by 11 WorldCat member libraries worldwide

Manual of radiochemical methods by D. G Olson( Book )

2 editions published in 1964 in English and held by 8 WorldCat member libraries worldwide

"The radiochemical methods used by the Analytical Branch, Atomic Energy Division of Phillips Petroleum Company for the determination of specific nuclides are described ..."
SPERT I destructive test program safety analysis report by A. H Spano( Book )

2 editions published in 1962 in English and held by 7 WorldCat member libraries worldwide

The water-moderated core used for destructive experiments is mounted in the Spent I open-type reactor vessel, which has no provision for pressurization or forced coolant flow. The core is an array of highly enriched aluminum clad, plate-type fuel assemblies, using four bladetype, gang-operated control rods. Reactor transients are initiated at ambient temperature by step-insentions of reactivity, using a control rod which can be quickly ejected from the core. Following an initial series of static measurements to determine the basic- reactor properties of the test core, a series of nondestructive, self-limiting power excursion tests was performed, which covered a reactor period range down to the point where minor fuel plate damage first occurred -approximately for a 10- msec period test. These tests provided power, temperature, and pressure data. Additional kinetic teste in the period region between 10 and 5 msec were completed to explore the region of limited core damage. Fuel plate damage results included plate distortion, cladding cracking, and fuel melting. These exploratory tests were valuable in revealing unexpected changes in the dependence of pressure, temperature, burst energy, and burst shape parameters on reactor period, although the dependence of peak power on reactor period was not significantly changed. An evaluation of hazards involved in conducting the 2- msec test, based on pessimistic assumptions regarding fission product release and weather conditions, indicates that with the procedural controls normally exercised in the conduct of any transient test at Spent and the special controls to be in effect during the destructive test series, no significant hazard to personnel or to the general public will be obtained. All nuclear operation is conducted remotely approximately 1/2 mile from the reactor building. Discussion is also given of the supervision and control of personnel during and after each destructive test, and of the plans for re-entry, cleanup, and restoration of the facility. (auth)
A method of determining the intermediate energy neutron dose by Dale E Hankins( Book )

2 editions published in 1961 in English and held by 6 WorldCat member libraries worldwide

The intermediate energy neutron flux existing outside the biological shielding of reactors has not been studied to any great extent previous to this time, because of the lack of an instrument capable of detecting neutrons in the intermediate energy range. The instrument used at the MTR utilizes polyethylene spheres of various sizes to give different amounts of moderation and absorption to the impinging neutrons. A procedure for the approximate determination of the relative number of intermediate energy and fast neutrons is given. By graphical methods the following information is obtained: (1) fraction of intermediate neutrons, (2) fraction of fast neutrons, and (3) the approximate average energy of the fast neutrons. Since the instrument described can be used to determine the thermal neutron flux independent of intermediate and fast fluxes, only one instrument is required to determine the neutron flux in all three energy ranges. Dose calculations indicate the intermediate range neutrons give a dose greater than the dose delivered by fast neutrons around the MTR-ETR reactors under normal operating conditions. (auth)
Physical and operational features of a pulsed continuous countercurrent liquid-solids contactor by E. S Grimmett( Book )

2 editions published in 1961 in English and held by 6 WorldCat member libraries worldwide

The physical and operational features of a rapidly pulsed, continuous, countercurrent, liquid- solids contactor are described. The contactor consists of a 2-in.-dia. column containing five contact stages. Solids feeding, contactor operation, and pulsing methods are described. Ion exchange resin flow rates up to 150 lb/hr/ft/sup 2/ and calcined aluminum oxide flow rates up to 300 lb/hr/ft/ sup 2/ were obtained while feeding water at rates up to 2000 lb/hr/ft/sup 2/. Optimum stage design should extend these rates considerably. The effects of pulse frequency and amplitude upon the column flow rate are described. Column ion exchange efficiencies were determined for the systems Cu--Na and Cu--H/sub 2/ at a cationic concentration of 0.1N, Sulfate was the common ion in the Cu--Na system and nitrate ion in the Cu--H/sub 2/ system. Stage efficiencies of greater than 27 to 62% were obtained. HTU values are aiso reported. (auth)
SPERT IV hazards summary report by F. L Bentzen( Book )

2 editions published in 1961 in English and held by 6 WorldCat member libraries worldwide

Spert IV is a large pool-type experimental facility for reactor kinetic studies. These studies will include power excursion and instability tests for a variety of reactor designs. Since the Spert IV experimental program requires the performance of tests which will approach, and may exceed the threshold of reactor destruction, the probability of occurrence of the maximum possible accident is not negligible compared with that of other possible accidents. The maximum possible accident for this facility is considered to be a severe nuclear excursion which results in the destruction of the reactor building and the release of 100% of the accumulated fission product inventory of the atmosphere in a steam cloud. The fission product source assumed in the analysis of this accident is an upper limit in view of the nature of the tests to be performed and the heat removal capacity of the system. This postulated accident is independent of the details of core and control system design and is valid for all cores anticipated for use in the experimental program. The major hazards present in the operation of this facility, the precautions to be taken to reduce the probability of an accident, and the consequences of the maximum possible accident are discussed. It is concluded that the proposed method of operation will minimize the hazard to operating personnel, and that the site location will make possible the operation of the Spent IV facility without hazard to the general public. (auth)
Containment of iodine-131 released by the RaLa process by G. K Cederberg( Book )

2 editions published in 1961 in English and held by 6 WorldCat member libraries worldwide

Uncontrolled releases of large amounts of iodine occurred during the early stages of RaLa operation at the ldaho Chemical Processing Plant. A ten- fold reduction in the iodine content of the off-gas was achieved by process modifications, primarily the addition of mercury salts to the acidic process solutions. An additional ten-fold reduction was obtained by installing an activated charcoal adsorption unit in series with the original iodine removal scrubber. The iodine content of particulate entrainment limited the over-all iodine removal efficiency of the revised RaLa off-gas iodine removal system. (auth)
Removal of tributyl phosphate and its degradation products from acidified uranyl nitrate solutions( Book )

2 editions published in 1964 in English and held by 6 WorldCat member libraries worldwide

The dissolution of iron and nickel in dilute aqua regia by Richard Douglas Cannon( Book )

2 editions published in 1961 in English and held by 6 WorldCat member libraries worldwide

In laboratory studies the dissolution of iron in dilute nitric - hydrochloric acid mixtures shows an apparent reaction order of -0.62 with respect to HCl. No apparent order value for HNO/sub 3/ can be determined over the concentration ranges studied. Nickel dissolutions show apparent orders of 1.4 with respect to the HCl and 4.2 for HNO/sub 3/. Activation energies determined from 50 to 80 deg C are not constant, ranging from l0 to 20 kcal per mole for both metals. (arth)
Propane vibrational analysis by G. D Marshall( Book )

2 editions published in 1962 in English and held by 5 WorldCat member libraries worldwide

Using the group vibratibn method of McMurry, the normal frequencies and coordinates of propane and three of its symmetrical deuterium substituted compounds were obtained. The force constants used were taken from a variety of previous works on hydrocarbons. The results give reasonable agreements with the experimental frequency and mode assignments of others. (auth)
An economic evaluation of ultimate disposal of liquid radioactive wastes by the fluidized bed calcination process by J. I Stevens( Book )

2 editions published in 1962 in English and held by 5 WorldCat member libraries worldwide

The costs of fluidized bed calcining of the acidic and re-acidified forms of Purex and Thorex wastes were determined. The wastes were assumed produced by a chemical-processing plant recovering unburned fuel from 1500 tons/ yr of U converter fuel at a burnup of 10,000 Mwd/ton and 270 tons/yr of Th converter fuel at 20,000 Mwd/ton. Also, investment costs for storage of the calcine in vented, air cooled, annular bins installed in underground concrete valuts were determined. The cost of fluidized bed calcining was determined at processing rates of 45, 80, and 75 gph for solids storage in bins varying from 3 to 22 in. thick and installed in underground concrete vaults containing 4, 12, 20, and 40 nested annular bins, each nest with an overall diameter of up to 12.5 ft. Aging had negligible effect on costs, except as it permitted thicker bins to be used. The lowest cost, 0.47 x 10/sup -2/ mills/kwh/sub e/, was for processing acidic Purex and Thorex wastes at 75 gph with storage in an underground concrete vault contnining 40 of the 12.5-ftdia. nested bin arrays. And the highest cost, 2.9 x 10/sup -2/ mills/kwh/sub e/, was for processing reacidified Purex and Thorex wastes at 45 gph with storage in an underground concrete vault containing 4 nested bin arrays. (auth)
Experimental and analytical reactivity studies of clean critical stainless steel cores by A. H Spano( Book )

2 editions published in 1961 in English and held by 5 WorldCat member libraries worldwide

ABS>The results are presented of critical water height measurements made on close-packed lattices of Spert III, highly enriched, plate-type, stainless- steel-clad fuel elements. Experiments were conducted with cores containing no control rods and with cores containing a single, fully-inserted control rod. The "clean critical" data obtained in these experiments were used to test the validity of various aspects of a four-group, diffusion theory analysis of the full scale Spert III reactor. The results of the analyses of the rod-free and single-rodded critical lattices show that for such stainless steel cores k/sub eff/ can be calculated to within 1% DELTA k and that the Spert III control rod worth is calculable to a few tenths % DELTA k. (auth)
MTR fast neutron flux measurements for cycle 146 by L. D Weber( Book )

2 editions published in 1962 in English and held by 5 WorldCat member libraries worldwide

The fast neutron fluxes in selected positions of the MTR were measured for Cycle 146. The measurements were made at the beginning, throughout, and at the end of the cycle (564 Mwd). Vertical traverses for each position monitors are shown. (auth)
Spectrographic determination of impurities in hafnium by B. E Ginther( Book )

2 editions published in 1961 in English and held by 5 WorldCat member libraries worldwide

A spectrographic method using d-c arc excitation in a controlled atmosphere was developed to analyze for seven impurity elements in radioactive hafnium samples. Analysis requires as little as 35 mg of hafnium oxide. (auth)
The merits of inherent shutdown vs mechanical shutdown of a plate-type, water-moderated and -reflected reactor in a runaway condition by F. L Bentzen( Book )

2 editions published in 1961 in English and held by 5 WorldCat member libraries worldwide

A small stainless-steel, plate-type, water-moderated reactor is subjected to large reactivity insertions in a study of the effectiveness of a fast safety system as compared with the self-shutdown characteristics of the reactor. The effectiveness of the mechanical safety system in controlling a reactor in a runaway condition is shown to be adequately described by the postulation of an effective delay time, which can be considered to be constant for all periods. The delay is comprised of the electronic release time and the time required for the rods to reach an effective position in teh core. In the system tested, the short effective delay time of 30 msec prevents reactor damage to periods as short as a few milliseconds. It is also shown that for safety systems with longer effective delay times, the ability of the reactor to cope with large reactivity insertions is determined by the inherent shutdown characteristics of the reactor and not by the mechanical system. (auth)
SPERT program review by Warren E Nyer( Book )

2 editions published in 1960 in English and held by 5 WorldCat member libraries worldwide

The Reactor Safety Program is centered on those problems associated with the operation of nuclear reactors which involve the possibility of extreme hazards. The program involves studies of reactor dynamics, chemical reactions, and reactor containment. The earliest large-scale experimental work was the Borax series of tests. The principal objectives of the Borax series were related to the feasibility of boiling reactors but included the study of the self- limiting properties of such systems when subjected to sudden large additions of reactivity. Studies on the maximum step and ramp additions of reactivity that can safely be introduced into a few selected types of reactor cores were completed. Spert-II will be used to examine the influence of prompt neutron lifetime and to study the influence of special factors connected with the use of heawy water. Spert-III wiII be used to assess the importance of pressure and temperature, as well as other special factors, in power plants operating with boilingand pressurized-water reactors. Spert-IV will be used for investigating self-induced oscillations. Extensive changes are proposed in the Spert-I program. (W.L.H.)
Tests of a vapor-space feed nozzle for calcining aluminum nitrate solutions in a fluidized bed by G. E Lohse( Book )

2 editions published in 1962 in English and held by 5 WorldCat member libraries worldwide

An investigation was conducted to determine the performance of a vapor- space feed nozzle which sprayed aluminum nitrate solution on the surface of a fluidized bed calciner. Results indicate that this type of feed system is satisfactory for calcining aqueous wastes from the processing of spent aluminum- type nuclear fueIs. Process and product control were achieved by adjusting the volumetric ratio of the air to the liquid fed to the nozzIe. The results obtained at various operating conditions are compared with those from a pneumatic atomizing nozzle submerged below the surface of the fluidized bed. (auth)
Analog solution of a model of the sources of elutriatable fines in the fluidized bed calcination process by Earl S Grimmett( Book )

2 editions published in 1963 in English and held by 5 WorldCat member libraries worldwide

A model is proposed which depicts the sources of elutriatable fines in the fluidized bed calcination process as being in two major groups, spray drying mechanisms and attrition mechanisms. Based on this model, equations are derived which express the rate of change of the concentration of a chemical tracer material in the elutriated fines, following introduction of the tracer into the feed and following its removal from the feed. This system has been simulated on an analog computer, and by matching the computer simulation to results from an actual calciner run, the rates of generation of fines by each of the two groups of mechanisms has been determined; the same technique results in an estimate of the amount of these fines remaining in the fluidized bed. Agreement between postulated results and results of actual experimental tests lends credence to the usefulness of this analytical technique. (auth)
ETR gamma heat generation measurements for cycles 27, 33, and 34 by L. D Weber( Book )

2 editions published in 1961 in English and held by 5 WorldCat member libraries worldwide

The gamma heat generations in selected positions of the ETR were measured for Cycles 27, 33, and 34. The measurements for Cycle 27 include data for the clean core and depleted core. Maximum gamma heat generation maps are presented for each cycle along with vertical traverses for all positions monitored. The measurements were made using a graphite- C0/sub 2/ ionization chamber. (auth)
 
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Alternative Names

controlled identityIdaho National Engineering Laboratory

National Reactor Testing Station (U.S.)

U.S. National Reactor Testing Station, Idaho Falls, Idaho

United States. National Reactor Testing Station, Idaho

United States. National Reactor Testing Station, Idaho Falls, Idaho

Languages
English (80)