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in publisher: "Hanford Engineering Development Laboratory"

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FFTF sodium and cover gas characterization and purification

The FFTF Primary and Secondary Heat Transport System (HTS) sodium is purified with cold traps which have packed crystallizers and external economizers. The Primary HTS cold trap is NaK cooled and the Secondary HTS cold traps are air cooled. The FFTF cold traps have maintained high purity in the sodium since sodium fill. Plant operational procedures during fill and initial sodium heatup to 800/sup 0/F were controlled to assure low release rates of impurities to the sodium. The FFTF sodium system… more

Date: February 1, 1980

Creator: McCown, J. J.; Bloom, G. R.; Meadows, G. E. & Mettler, G. W.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Data systems in FFTF and EBR-II

This paper describes the Data System used to monitor operation and collect experimental data in FFTF. This data system has evolved since initial inception from a relatively simple, single computer system monitoring a relatively few (approx. 1000) instrument channels important for operation to one which has increased capability to support the long-range testing needs in FFTF. The system, while still relatively simple, now contains multiple computers which normally perform independent functions. … more

Date: February 1, 1980

Creator: Warrick, R. P. & Ritter, W. M.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Swelling in simple ferritic alloys irradiated to high fluence contribution to ADIP report

A series of Fe-Cr-C-Mo simple alloys has been measured for density change as a function of irradiation in EBR-II over the temperature range 400 to 650/sup 0/C to fluences as high as 2.13 x 10/sup 23/ n/cm/sup 2/ (E > 0.1 MeV) or 105 dpa. The highest swelling was found in an Fe-12Cr binary alloy, 4.72%, after 1.87 x 10/sup 23/ n/cm/sup 2/ or 95 dpa at 425/sup 0/C, which corresponds to a swelling rate of 0.06% dpa. This peak swelling rate value can be used to define swelling predictions for comme… more

Date: January 1, 1983

Creator: Gelles, D. S. & Meinecke, R. L.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Fuel debris assessment for Three Mile Island Unit 2 (TMI-2) reactor recovery by gamma-ray and neutron dosimetry

As a result of the accident on March 28, 1979, fuel debris was dispersed into the primary coolant system of the Three Mile Island Unit 2 (TMI-2) reactor. Location and quantification of fuel debris is essential for TMI-2 recovery. TMI-2 fuel debris assessments can be carried out nondestructively by neutron and gamma-ray dosimetry. Efforts to date have been directed toward fuel debris characterization of the makeup and purification demineralizers, will maintain reactor coolant water purity. Two h… more

Date: August 22, 1983

Creator: Gold, R.; Roberts, J. H.; McNeece, J. P.; Kaiser, B. J.; Ruddy, F. H.; Preston, C. C. et al.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Acid digestion of combustible radioactive wastes

The following conclusions resulted from operation of Radioactive Acid Digestion Test Unit (RADTU) for processing transuranic waste: (1) the acid digestion process can be safely and efficiently operated for radioactive waste treatment.; (2) in transuranic waste treatment, there was no detectable radionuclide carryover into the exhaust off-gas. The plutonium decontamination factor (DF) between the digester and the second off-gas tower was >1.5 x 10/sup 6/ and the overall DF from the digester t… more

Date: March 1, 1982

Creator: Allen, C. R.; Lerch, R. E.; Crippen, M. D. & Cowan, R. G.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Frank loop formation in irradiated metals in response to applied and internal stresses

The Frank loop and dislocation microstructures developed in three face-centered cubic alloys during fast reactor irradiation have been examined to determine the influence of applied and internally-generated stress on loop evolution. It is shown that anisotropic stresses generate a corresponding anisotropy of Frank loop populations on the four close-packed planes. The loop populations thus represent a microstructural record of the irradiation creep processes in action. The ease of interpreting t… more

Date: April 1, 1980

Creator: Gelles, D. S.; Garner, F. A. & Brager, H. R.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Fuel and cladding tests for fuel failure safety analysis. [LMFBR]

Three systems for testing fuel pin cladding were developed to support the determination of the mode and location of cladding failure during transient overpower events or transient undercooled overpower (TUCOP) conditions. The TUCOP FCTT system consists of exposing cladding specimens to thermal and loading conditions typical of TUCOP events. The Mandrel Loading Test (MLT) system was designed to produce cladding deformation and failure by internal mechanical interaction loading of a heated claddi… more

Date: January 1, 1982

Creator: Hunter, C. W.; Johnson, G. D.; Hu, W. L.; Cannon, N. S.; Feigenbutz, L. V.; Hinman, C. A. et al.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

HEDL sodium vapor deposit experience. [LMFBR]

Sodium vapor deposits can affect reactor component operation and maintenance. Recorded cases include plugged cover gas lines and cementation of rotating components or sliding surfaces. Deposits found on plant scale components after testing in sodium were measured. Laboratory tests show the effect of Na pool temperature and condenser geometry on deposit accumulation rates and viewport fogging.

Date: December 1, 1979

Creator: Funk, C.W.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Safety aspects of fast reactor fuels. [LMFBR]

Design requirements and performance characteristics of fuel pins for LMFBR reactors under accident conditions are discussed.

Date: January 1, 1977

Creator: Hanson, J.E.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Preirradiation microstructural characterization of FFTF mixed oxide fuel

Charts, drawings, graphs, and photographs are presented concerning the research program to evaluate potential for fuel to undergo densification during irradiation, to assure PuO/sub 2/ homogeneity in mixed oxide fuel, to provide data base for pre-/post-irradiation comparisons, and to evaluate effect of fuel fabrication conditions.

Date: January 1, 1981

Creator: Rasmussen, D. E. & Schaus, P.S.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Development of a modified diffusion type carbon activity meter for liquid sodium

A high sensitivity automated carbon activity meter has been developed by combining elements of technology used in other instruments. The basic principle is the diffusion of carbon through an iron membrane driven by the concentration gradient between the sodium being measured and the sweep gas. The membrane used is similar to that used by Harwell workers, i.e., a coil of small diameter iron tubing with an oxide coating on the inner surface. A sweep gas of helium is used to pick up the carbon oxi… more

Date: January 1, 1980

Creator: Barton, G. B.; Cook, W. V. & McCauley, D. L.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Overview of the fast reactors fuels program. [LMFBR]

Each nation involved in LMFBR development has its unique energy strategies which consider energy growth projections, uranium resources, capital costs, and plant operational requirements. Common to all of these strategies is a history of fast reactor experience which dates back to the days of the Manhatten Project and includes the CLEMENTINE Reactor, which generated a few watts, LAMPRE, EBR-I, EBR-II, FERMI, SEFOR, FFTF, BR-1, -2, -5, -10, BOR-60, BN-350, BN-600, JOYO, RAPSODIE, Phenix, KNK-II, … more

Date: April 1, 1980

Creator: Evans, E.A.; Cox, C.M.; Hayward, B.R.; Rice, L.H. & Yoshikawa, H.H.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Operation of the radioactive acid digestion test unit

The Radioactive Acid Digestion Test Unit (RADTU) has been constructed at Hanford to demonstrate the application of the Acid Digestion Process for treating combustible transuranic wastes and scrap materials. The RADTU with its original tray digestion vessel has recently completed a six-month campaign processing potentially contaminated nonglovebox wastes from a Hanford plutonium facility. During this campaign, it processed 2100 kg of largely cellulosic wastes at an average sustained processing r… more

Date: January 1, 1980

Creator: Blasewitz, A. G.; Allen, C. R.; Lerch, R. E.; Ely, P. C. & Richardson, G. L.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Correlation of macroscopic material properties with microscopic nuclear data

Two primary irradiation-induced changes occur during neutron irradiation: the displacement of atoms forming crystal defects and the transmutation of atoms into either gaseous or solid products. The material scientist studying irradiation damage to material by fusion-produced neutrons is faced with several questions: Is the nature of high-energy (14-MeV) displacement damage the same as or different from that caused by fission neutrons (< 2 MeV). How do the high helium concentrations expected in … more

Date: December 18, 1981

Creator: Simons, R.L.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Summary report of fuel rod displacement sensor for LOFT

Qualification tests conducted for a period of 700 hours of each of three displacement measuring (LVDT) sensors confirmed applicability of the design for use in the Loss-of-Fluid-Test (LOFT) reactor. Operationally, the sensor satisfies all specified requirements for LOFT. Even for imposed temperature transients at rates up to 100/sup 0/F/s, the indicated displacement remained within the allowed maximum error band of +-10% of reading. The 0.625-inch O.D. by 5.5-inch long sensor exhibited a linear… more

Date: January 1, 1980

Creator: Billeter, T.R.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Effects of composition on the in-reactor creep of AISI 316

In-reactor tests designed to provide information on the relationship between compositional variations and irradiation-induced swelling and creep have achieved an exposure of 4.6 x 10/sup 22/ n/cm/sup 2/ (E > 0.1 MeV) at 450/sup 0/C. Postirradiation diametral measurements of pressurized tube specimens have indicated that irradiation-induced creep of 316 stainless steel can be modified by compositional variations of minor alloying elements. There is a general trend for specimens with higher swell… more

Date: August 1, 1979

Creator: Bates, J.F. & Gilbert, E.R.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Automated amperometric plutonium assay system

The amperometric titration for plutonium assay has been used in the nuclear industry for over twenty years and has been in routine use at the Hanford Engineering Development Laboratory since 1976 for the analysis of plutonium oxide and mixed oxide fuel material for the Fast Flux Test Facility. It has proven itself to be an accurate and reliable method. The method may be used as a direct end point titration or an excess of titrant may be added and a back titration performed to aid in determinati… more

Date: January 1, 1985

Creator: Burt, M.C.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Physically based model for helium release from irradiated boron carbide

The model is based on the nucleation of nonequilibrium helium bubbles under high pressures. The bubbles subsequently act as traps and grow as the result of gas atom diffusion. Model predictions are compared with bubble densities, sizes, and helium release characteristics of irradiated boron carbide.

Date: January 1, 1979

Creator: Beyer, C. E.; Hollenberg, G. W. & Duran, S. A.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Facilities projects performance measurement system. [Fuels and Materials Examination Facility (EMEF); Fusion Material Irradiation Test (FMIT) facility]

The two DOE-owned facilities at Hanford, the Fuels and Materials Examination Facility (FMEF), and the Fusion Materials Irradiation Test Facility (FMIT), are described. The performance measurement systems used at these two facilities are next described. (DLC)

Date: October 9, 1979

Creator: Erben, J.F.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Materials interaction test summary description

The Materials Interaction Test is designed to provide early scoping data on host rock performance and interaction between nuclear waste canister materials and host repository media under conditions representative of expected disposal environments. Capsules containing these materials were put in a spent fuel assembly and subsequently placed in a disposal test to study behavior in a low-level radiation environment at temperaures expected to range between 300 to 400/sup 0/F. Thermal control capsul… more

Date: January 1, 1980

Creator: Krogness, J.C.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

ENDF/B-5 fission product cross section evaluations

Cross section evaluations were made for the 196 fission product nuclides on the ENDF/B-5 data files. Most of the evaluations involve updating the capture cross sections of the important absorbers for fast and thermal reactor systems. This included updating thermal values, resonance integrals, resonance parameter sets, and fast capture cross sections. For the fast capture results generalized least-squares calculations were made with the computer code FERRET. Input for these cross section adjustm… more

Date: December 1, 1979

Creator: Schenter, R. E. & England, T. R.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Ultra high vacuum fracture and transfer device for AES analysis of irradiated austenitic stainless steel

An ultrahigh vacuum fracture and transfer device for analysis of irradiated and non-irradiated SS 316 fuel cladding is described. Mechanical property tests used to study the behavior of cladding during reactor transient over-power conditions are reported. The stress vs temperature curves show minimal differences between unirradiated cladding and unfueled cladding. The fueled cladding fails at a lower temperature. All fueled specimens failed in an intergranular mode. (FS)

Date: January 1, 1980

Creator: Urie, M.W.; Panayotou, N.F. & Robinson, J.E.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Uranium Plutonium Oxide Fuels

Uranium plutonium oxide is the principal fuel material for liquid metal fast breeder reactors (LMFBR's) throughout the world. Development of this material has been a reasonably straightforward evolution from the UO/sub 2/ used routinely in the light water reactor (LWR's); but, because of the lower neutron capture cross sections and much lower coolant pressures in the sodium cooled LMFBR's, the fuel is operated to much higher discharge exposures than that of a LWR. A typical LMFBR fuel assembly … more

Date: January 1, 1981

Creator: Cox, C. M.; Leggett, R. D. & Weber, E. T.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

2200/sup 0/C fuel centerline thermocouples for the LOFT program

The technology as well as commercial suppliers have been developed for high temperature thermocouples for the Loss-of-Fluid-Test (LOFT) program. Two types of thermocouples were developed and tested. Model B units contained a 1/16-inch OD 24-inch long Mo/Re sheath probe and were capable of temperature measurement to 1550/sup 0/C. Model A units contained a 1/16-inch OD 41-inch long W/Re-augmented sheath probe and were capable of temperature measurement to 2200/sup 0/C.

Date: July 1, 1979

Creator: Cannon, C. P. & Lunghofer, J.

Item Type: Article

Partner: UNT Libraries Government Documents Department