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Irradiation Testing of Enrico Fermi Prototype Fuel Pins in the CP-5, 1957-1959

Description: Report issued by the APDA over studies conducted on the irradiation of fuel pins in nuclear reactors. As stated in the introduction, "results of these tests have verified predicted high-temperature allowable burn-ups and showed that under certain conditions, excessive swelling could occur at low temperatures" (p. 5). This report includes tables, illustrations, and photographs.
Date: April 1960
Creator: Silliman, M. A.; Shoudy, A. A.; Blessing, W. G. & Huebotter, P. R.
Partner: UNT Libraries Government Documents Department

Experimental evaluation of fission-gas release in LMFBR subassemblies using an electrically heated test section with sodium as coolant

Description: A description is given of an out-of-pile experiment which simulated fission-gas release in current-design uranium-oxide fuel subassemblies of liquid- metal-cooled fast breeder reactors (LMFBR's) and which was performed to evaluate the potential for pin-to-pin failure propagation due to thermal transients induced in adjacent fuel pins. A sodium-cooled test section containing three electrically heated pins was used. Gas (angon or xenon), injected as a jet through a needle protruding into the flow cross-sectional area of the test section, was made to impinge on one of the heater pins. Data are presented regarding the measured cladding-temperature rise and the calculated local heat- transfer coefficient in the impingement area, with the following parameters: gas type, needle internal diameter, heat flux, coolant flow rate, gas-plenum pressure and temperature, and axial location with respect to the gas jet. The cladding- temperature rises measured represent upper values, since the conditions under which they were obtained are conservative. There are two reasons for this: (a) The gasrelease rates correspond to those that would prevail if the internal resistance to the flow of gas, between the gas plenum and the point of release of the fuel pin, were negligibly small; (b) the tests were performed under steady- state conditions, whereas, under actual reactor conditions, the gas-release rates would be decreasing with time because of the fixed fission-gas inventory. For a narrow range of gas-release rates under subsonic and near-subsonic conditions, cladding-temperature rises were found to occur in the impingement area, for the above conservative conditions, of up to approximates 240 deg C at a heat flux of 250 W/cm/sup 2/. (auth)
Date: July 1, 1973
Creator: Wilson, R.E.; van Erp, J.B.; Chawla, T.C.; Kimont, E.L. & Baldwin, R.D.
Partner: UNT Libraries Government Documents Department

Sharing of the RPI Reactor Critical Facility (RCF). Final summary report, January 1988--September 1995

Description: Rensselaer Polytechnic Institute (RPI) has participated for a number of years in Sharing of the Reactor Critical Facility (RCF) under the U.S. Department of Energy University Reactor Sharing Program. In September of each year a Sharing invitation is sent to 92 public and private high schools and to 74 colleges and universities within about a 3 hour drive to the RCF (Appendix B). Each year about 10 such educational institutions send groups to share the RCF.
Date: September 1, 1995
Creator: Harris, D.R.
Partner: UNT Libraries Government Documents Department

A Deterministic Study of the Deficiency of the Wigner-Seitz Approximation for Pu/MOX Fuel Pins

Description: The Wigner-Seitz pin-cell approximation has long been applied as a modeling approximation in analysis of UO2 lattice fuel cells. In the past, this approximation has been appropriate for such fuel. However, with increasing attention drawn to mixed-oxide (MOX) fuels with significant plutonium content, it is important to understand the implications of the approximation in a uranium-plutonium matrix. The special geometric capabilities of the deterministic NEWT computer code have been used to assess the adequacy of the Wigner-Seitz cell in such an environment, as part of a larger study of computational aspects of MOX fuel modeling. Results of calculations using various approximations and boundary conditions are presented, and are validated by comparison to results obtained using KENO V.a and XSDRNPM.
Date: September 27, 1999
Creator: DeHart, M.D.
Partner: UNT Libraries Government Documents Department

Material accountancy for metallic fuel pin casting

Description: The operation of the Fuel Conditioning Facility (FCF) is based on the electrometallurgical processing of spent metallic reactor fuel. The pin casting operation, although only one of several operations in FCF, was the first to be on-line. As such, it has served to demonstrate the material accountancy system in many of its facets. This paper details, for the operation of the pin casting process with depleted uranium, the interaction between the mass tracking system (MTG) and some of the ancillary computer codes which generate pertinent information for operations and material accountancy. It is necessary to distinguish between two types of material balance calculations -- closeout for operations and material accountancy for safeguards. The two have much in common, for example, the mass tracking system database and the calculation of an inventory difference, but, in general, are not congruent with regard to balance period and balance spatial domain. Moreover, the objective, assessment, and reporting requirements of the calculated inventory difference are very different in the two cases.
Date: August 1, 1995
Creator: Bucher, R.G.; Orechwa, Y. & Beitel, J.C.
Partner: UNT Libraries Government Documents Department

MOX Average Power Test 30 GWd/MT PIE: Quick Look

Description: This report summarizes the early results of the post irradiation examination of the 30 GWd/MT MOX Average Power Test Capsules (numbers 3 and 10). The purpose of this preliminary examination is to document and monitor the progress of the MOX Average Power Test Irradiation. The capsules and their fuel pins were found to be in excellent condition. Measurement of the fission gas release fraction (about 1.50 to 2.26%), preliminary fuel stack gamma scan measurements, and preliminary fuel pin diameter measurements indicate that the fuel is behaving as expected.
Date: February 14, 2001
Creator: MORRIS, RN
Partner: UNT Libraries Government Documents Department

Reactor whole core transport calculations without fuel assembly homogenization

Description: The variational nodal method is generalized by dividing each spatial node into a number of triangular finite elements designated as subelements. The finite subelement trail functions allow for explicit geometry representations within each node, thus eliminating the need for nodal homogenization. The method is implemented within the Argonne National Laboratory code VARIANT and applied to two-dimensional multigroup problems. Eigenvalue and pin-power results are presented for a four-assembly OECD/NEA benchmark problem containing enriched U{sub 2} and MOX fuel pins. Our seven-group model combines spherical or simplified spherical harmonic approximations in angle with isoparametric linear or quadratic subelement basis functions, thus eliminating the need for fuel-coolant homogenization. Comparisons with reference seven-group Monte Carlo solutions indicate that in the absence of pin-cell homogenization, high-order angular approximations are required to obtain accurate eigenvalues, while the results are substantially less sensitive to the refinement of the finite subelement grids.
Date: October 18, 2002
Creator: Tsoulfanidis, Nicholas; Lewis, Elmer; Smith, M.A.; Palmiotti, G. & Taiwo, T.A.
Partner: UNT Libraries Government Documents Department

CHIT: a cost accounting program for postirradiation examinations of fast breeder reactor materials

Description: CHIT is the Los Alamos Scientific Laboratory's cost accounting computer program for nondestructive and destructive examinations of irradiated fuel pins. The program allows immediate retrieval of fuel pin examination information and provides itemized listings for completed and projected fuel pin examinations, detailed cost accounting summaries for each investigator, fuel pin examinations during a specified time interval, and various subsets of the information. CHIT has been in successful operation for the past two years, providing precise information on cost accounting more efficiently than possible with a manual technique. (auth)
Date: September 1, 1975
Creator: Phillips, J.R. & Dowler, K.E.
Partner: UNT Libraries Government Documents Department


Description: A coupled TH/Neutronics/CRUD framework, which is able to simulate the CRUD deposits impact on CIPS phenomenon, was described in this paper. This framework includes the coupling among three essential physics, thermal-hydraulics, CRUD and neutronics. The overall framework was implemented by using the CFD software STAR-CCM+, developing CRUD codes, and using the neutronics code DeCART. The coupling was implemented by exchanging data between softwares using intermediate exchange files. A typical 3 by 3 PWR fuel pin problem was solved under this framework. The problem was solved in a 12 months length period of time. Time-dependent solutions were provided, including CRUD deposits inventory and their distributions on fuels, boron hideout amount inside CRUD deposits, as well as power shape changing over time. The results clearly showed the power shape suppression in regions where CRUD deposits exist, which is a strong indication of CIPS phenomenon.
Date: April 1, 2012
Creator: Zou, Ling; Zhang, Hongbin; Gehin, Jess & Kochunas, Brendan
Partner: UNT Libraries Government Documents Department

FUELPIN: a data retrieval system for nuclear fuel pin information

Description: The Fortran IV computer code FUELPIN was developed to assist in the surveillance of large numbers of nuclear fuel pins. Using sixteen levels of sorting and thirty-one key pin characteristics, the computer code sorts through large blocks of pin data to determine those pins having the desired characteristics. Allowance is also made for miscellaneous information on (1) fuel type, (2) clad material, (3) bond data, and (4) general pin information. Upon execution the blocks of fuel pin information are inspected to insure that the data are credible, i.e., between experimenter specified limits. Octal stops are provided, numbered, and discussed in the codes comment section so as to block all paths of code execution known to indicate operational error. All parameter sort information is also inspected for potential input error with some minor correctional measures accomplished upon detection of an error condition. Though limited to blocks of two hundred and fifty pins per run, large numbers of pins may be efficiently examined through problem stacking and proper use of a built in computer time economizing scheme. (auth)
Date: January 1, 1974
Creator: Walters, K.L.; Barner, J.O. & Green, J.L.
Partner: UNT Libraries Government Documents Department


Description: This report summarizes the design of the ATR MOX Test Fuel Pin Measuring Device. This device makes use of four Magnescale probes and a precision sliding table to make three-dimensional measurements of a short fuel pin (approximately 8 inches) with an accuracy of better than 0.0003 inches. Mathematical fitting is then used to determine the diameter and bowing of the fuel pin as a function of length. This device is currently being applied to fuel pins irradiated in the Advanced Test Reactor (ATR) as part of the Light Water Mixed Oxide Fuel Irradiation Test sponsored by the Department of Energy.
Date: March 13, 2001
Creator: MORRIS, R.N.
Partner: UNT Libraries Government Documents Department