UO{sub 3} Plant cold shakedown run plan: No. C-1 (open access)

UO{sub 3} Plant cold shakedown run plan: No. C-1

This report presents the cold shakedown run for the UO{sub 3} plan. One complete batch conversion will be made in each of the eighteen Calcining Pots using unirradiated uranium food solution. The objectives of this series of conversions are as follows. A mechanical test of the conversion units; a shakedown of the unloading, pulverizing and material handling equipment; a functional test of the Nitro Acid Absorber system operating at approximately 5 to 20% of its design capacity; the determination of the optimum temperature and time cycle conditions for 60% UNH feed solution. These conditions may be based upon calcination of the initial charge of 60% UNH solution to form UO{sub 3}, in one pot; a confirmation of the calibration of instruments; and to provide operating experience and process know-how.
Date: November 13, 1951
Creator: Raab, G. J. & Oberg, G. C.
System: The UNT Digital Library
Results of experimental tests simulating supply pressure decrease in a K process tube (open access)

Results of experimental tests simulating supply pressure decrease in a K process tube

Simultaneous reduction of coolant to several or all reactor tubes raises concern not only for the adequacy of protection in the individual process tube but also the reactor as a whole. In event of such flow reduction, the heat generation does not decrease until at least 1.4 seconds have elapsed following the accident. Thus, the water temperature from each tube will rise, and result in an increase in the bulk water temperature. If the increase in bulk water temperature is such that saturation temperature at the top of downcomer is reached, pressurization may occur at that point and exceed the maximum recommended working pressure limit (approximately 1 to 2 psig). The purpose of this report is to present experimental data on a series of tests which were made to simulate flow reductions to a K type process tube by simulated front header pressure decreases.
Date: November 13, 1957
Creator: Toyoda, K. G. & Calkin, J. F.
System: The UNT Digital Library
Project Pluto Ground Test Facilitiees. Design Criteria 1959 Addedum to TR 153-12 (open access)

Project Pluto Ground Test Facilitiees. Design Criteria 1959 Addedum to TR 153-12

None
Date: November 13, 1959
Creator: Smith, L. C.; Levin, Harry & Johnsen, E. G.
System: The UNT Digital Library
Efficiency of HRT Pressurizer Heater Insulation (open access)

Efficiency of HRT Pressurizer Heater Insulation

None
Date: November 13, 1956
Creator: Hughes, R. F.
System: The UNT Digital Library
EXPLOSIVE REACTIONS DURING REPROCESSING OF REACTOR FUELS CONTAINING URANIUM AND ZIRCONIUM OR NIOBIUM (open access)

EXPLOSIVE REACTIONS DURING REPROCESSING OF REACTOR FUELS CONTAINING URANIUM AND ZIRCONIUM OR NIOBIUM

Small particles of zirconinm formed during mechancal operations have caused serious industrial explosions. Particles of this type will not be encountered during aqueous chemical reprocessing. However, small panticles of metallic phases rich in zirconium or niobium, produced by selective leaching of a more reactive uranium-rich phase, can enter into violently explosive reactions. The conditions under which explosions with zirconium-bearing alloys may be expected during chemical reprocessing have been defined in the literatare. The uranium-zirconiaum alloys containing less than 30 wt.% zirconium are hazardous when they contact nitric acid. Laboratory work has shown that potentially explosive zirconium alloys may be safely dissolved in nitric acid if enough fluoride ion is added to maintain a mole ratio of fluoride to dissolved zirconium of four. Niobium-bearing fuel alloys can also explode after contacting nitric acid, but the conditions which produce explosions have not yet been studied thoroughly. Dissolution studies with the EBWR alloy (93.5% U, 5% Zr, 1.5% Nb) indicate that hazardous niobium alloys can also be processed safely in nitric acid by addition of enough fluoride to prevent formation of surface deposits. The ternary phase diagram for zirconium -uranium -oxygen shows that the epsilon phase is unstable at the interface between a …
Date: November 13, 1958
Creator: Gens, T.A.
System: The UNT Digital Library
ACTIVITIES IN LIQUID AND SOLID BINARY METAL SYSTEMS. Progress Report on Research Program for February 1, 1956 to January 31, 1957 (open access)
Proton distribution in heavy nuclei (open access)

Proton distribution in heavy nuclei

None
Date: November 13, 1953
Creator: Johnson, M.H & Teller, E.
System: The UNT Digital Library
DENITRATION OF URANYL NITRATE. Quarterly Report for Period August 10- November 10, 1951 (open access)

DENITRATION OF URANYL NITRATE. Quarterly Report for Period August 10- November 10, 1951

None
Date: November 13, 1951
Creator: Reilly, V.J.
System: The UNT Digital Library
URANIUM CHEMISTRY OF RAW MATERIALS SECTION PROGRESS REPORT FOR JULY 1, 1952 TO SEPTEMBER 30, 1952. PART I. URANIUM FROM LIGNITES (open access)

URANIUM CHEMISTRY OF RAW MATERIALS SECTION PROGRESS REPORT FOR JULY 1, 1952 TO SEPTEMBER 30, 1952. PART I. URANIUM FROM LIGNITES

None
Date: November 13, 1952
Creator: Brown, K.B.; Schimmel, F.A. & Nelson, R.C.
System: The UNT Digital Library
Radiation Stability of Aqueous Fuel Systems. Material for Revised Reactor Handbook (open access)

Radiation Stability of Aqueous Fuel Systems. Material for Revised Reactor Handbook

None
Date: November 13, 1956
Creator: Hochanadel, C. J.
System: The UNT Digital Library
INTERMETALLIC COMPOUNDS BETWEEN LITHIUM AND LEAD. V. BRILLOUIN POLYHEDRA OF THE VARIOUS PHASES (open access)

INTERMETALLIC COMPOUNDS BETWEEN LITHIUM AND LEAD. V. BRILLOUIN POLYHEDRA OF THE VARIOUS PHASES

Brillouin polyhedra for the intermetallic compounds of lithium and lead were determined using the zone theory. From these determinations, predictions and explanations of some electromagmetic and structural properties of the intermetallic compounds were made. (For Part IV see UCRL-4973.) (C.J.G.)
Date: November 13, 1959
Creator: Ramsey, W J & Jepson, J O
System: The UNT Digital Library
ZIRCEX KINETICS AND URANIUM LOSS STUDY (open access)

ZIRCEX KINETICS AND URANIUM LOSS STUDY

A study was made of the effects of temperature, impurities in the hydrogen chloride, flow rates, and niobium content on both the reaction rates and insoluble uranium losses in the Zircex Process is presented. (W.L.H.)
Date: November 13, 1957
Creator: Carter, T. J., Jr. & Stone, R. A.
System: The UNT Digital Library
Monte Carlo Research Series: Monte Carlo Program for a Linear Reactor With Void Gaps (open access)

Monte Carlo Research Series: Monte Carlo Program for a Linear Reactor With Void Gaps

A Monte Carlo calculation for computing the diffusion coefficient and diffusion length in a linear system, with alternate solid and void segments is described. The program code is for the IBM 704. (auth)
Date: November 13, 1957
Creator: Beeler, J. R., Jr.; Nelson, R. H. & Dyer, P. A.
System: The UNT Digital Library