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Acoustic detection of the collapse of a sodium vapor bubble in an infinite sea of sodium

Description: A discussion of the problem of sodium vapor bubble collapse is presented. The physics of vapor collapse is presented in light of the work by Peppler et al. Theoretical estimates of the sound source level based on the work by Rayleigh and Judd are compared to an approximate pressure-volume work approach and recent experimental observations. Reactor ambient noise and transmission loss considerations are presented in regard to their impact on this detection problem. A methodology is proposed which considers the importance of the sound source level, ambient noise, transmission loss and a detection threshold and provides a means by which the feasibility of sodium vapor bubble collapse detection in an operating LMFBR may be assessed. The interrelationships between the detection threshold and the probability of detection and false alarm are discussed and applied to a standard acoustic square law detection system. This analysis clearly illustrates that the feasibility of such a detection system is strongly dependent on the knowledge of sound source levels, ambient noise levels and the transmission loss between the source and receiver. Furthermore, requirements of a high degree of probability of detection and a low probability of false alarm were found to require a high signal to noise ratio for a single sensor system but that the probability of false alarm requirement could be relaxed for systems multiple independent sensors. Finally, the need for additional experimental and theoretical information is presented in terms of sound source levels, ambient noise and a means for determining transmission loss. (auth)
Date: December 1, 1975
Creator: Carey, W. M.
Partner: UNT Libraries Government Documents Department

Flow-induced vibration in LMFBR steam generators: a state-of-the-art review

Description: This state-of-the-art review identifies and discusses existing methods of flow-induced vibration analysis applicable to steam generators, their limitations, and base-technology needs. Also included are discussions of five different LMFBR steam-generator configurations and important design considerations, failure experiences, possible flow-induced excitation mechanisms, vibration testing, and available methods of vibration analysis. The objectives are to aid LMFBR steam-generator designers in making the best possible evaluation of potential vibration in steam-generator internals, and to provide the basis for development of design guidelines to avoid detrimental flow-induced vibration. (auth)
Date: May 1, 1975
Creator: Shin, Y.S. & Wambsganss, M.W.
Partner: UNT Libraries Government Documents Department

Some findings from FFTF piping and component design analyses

Description: A number of questions that have been commonly raised during elevated temperature design of FFTF components and pipelines are identified and discussed. Although the questions do not lend themselves to simple answers, some guidance based on analysis findings is given. Based upon the limited data developed, uniaxial stress relaxation data can give a reasonable pattern of structural creep damage as a function of time. However, the creep damage magnitude may be as much as a factor of two too low. Other geometries and/or loading may show much larger variations between the uniaxial and complex hardware creep damage response. (auth)
Date: September 1, 1975
Creator: Severud, L.K.; Weiner, E.O. & Winkel, B.V.
Partner: UNT Libraries Government Documents Department

Evaluated decay-scheme data for the ILRR program

Description: The half-lives and $gamma$-ray intensities associated with radioactive decay have been evaluated for nuclides of interest to the Interlaboratory LMFBR Reaction Rate program. The results indicate that for most of the isotopes the decay parameters are known sufficiently well to meet the ILRR goals of 2$sup 1$/ $sub 2$ or 5 percent accuracy in reaction rate measurements. (auth)
Date: January 1, 1975
Creator: Helmer, R.G. & Greenwood, R.C.
Partner: UNT Libraries Government Documents Department

Central worth and spectral measurements in the GCFR. Phase I assembly

Description: Central fission and capture rates, the central neutron spectrum and the reactivity worths of small samples were measured at the core center of the GCFR Phase I Assembly, the initial benchmark GCFR mockup assembly. Results of these measurements and comparisons with calculations are reported. (auth)
Date: November 1, 1975
Creator: Morman, J.A.; Bhattacharyya, S.K.; Smith, D.M.; McKnight, R.D.; Yule, T.J. & Bohn, E.M.
Partner: UNT Libraries Government Documents Department

Gas cooled fast reactor benchmark critical assembly

Description: The GCFR Phase I assembly is the initial Gas-Cooled Fast Reactor Benchmark assembly on the ZPR-9 reactor at Argonne National Laboratory. It represents the first full scale mockup of a GCFR ever assembled. It is a clean, simple geometry benchmark reference for the 300 MW(e) GCFR Demonstration Plant designed by General Atomic Company. A description and the evaluated specifications (zero-excess reactivity critical mass and dimensions) of the benchmark assembly are presented. (auth)
Date: November 1, 1975
Creator: Bhattacharyya, S.K.; McKnight, R.D.; Robinson, W.R.; Bohn, E.M.; Rusch, G.K.; Martens, F.H. et al.
Partner: UNT Libraries Government Documents Department

Summary of failure analysis activities at Brookhaven National Laboratory

Description: Brookhaven National Laboratory has for many years conducted examinations related to the failures of nuclear materials and components. These examinations included the confirmation of root cause analyses, the determination of the causes of failure, identification of the species that accelerate corrosion, and comparison of the results of nondestructive examinations with those obtained by destructive examination. The results of those examinations, which had previously appeared in various formats (formal and informal reports, journal articles, etc.), have been collected together and summarized in the present report. The report is divided into sections according to the general subject matter (for example, corrosion, fatigue, etc.). Each section presents summaries of the information contained in specific reports and publications, all of which are fully identified as to title, authors, report number or journal reference, date of publication, and FIN number under which the work was performed.
Date: October 1, 1996
Creator: Cowgill, M.G.; Czajkowski, C.J. & Franz, E.M.
Partner: UNT Libraries Government Documents Department

Reflector dowel strength test, Fort St. Vrain

Description: The strength of the 44.45 mm (1.75 in.) diameter Fort St. Vrain (FSV) reflector dowel for loads directed radially inward toward the center of the element was measured. For a statically applied load, the strength exceeded 5783 N (1300 lb) in direct shear. This strength remained after load cycling 100 times to 4448 N (1000 lb), 10 times to 4893 N (1100 lb), 10 times to 5338 N (1200 lb), and two times to 5783 N (1300 lb). Typically, the deflection to ultimate failure was approximately 1.0 mm (0.04 in.). At about 3316 N (750 lb) and 0.20 mm (0.008 in.) deflection, one of the webs between the dowel and a coolant hole cracked, apparently redistributing the load. No further failure occurred up to the ultimate load of 5783+ N (1300+ lb). (auth)
Date: October 31, 1975
Creator: Doll, D.W.
Partner: UNT Libraries Government Documents Department

ENDF/B-VII.0 Data Testing for Three Fast Critical Assemblies

Description: In this report we consider three fast critical assemblies, each assembly is dominated by a different nuclear fuel: Godiva (U235), Jezebel (Pu239) and Jezebel23 (U233) [1]. We first show the improvement in results when using the new ENDF/B-VII.0 data [2], rather than the older, now frozen, ENDF/B-VI.8 data [3]. We do this using what we call a one code/ multiple library approach, where results from one code (MCNP) are compared using two different data libraries (ENDF/B-VII.0 and VI.8). Next we show that MCNP results are not specific to this one code by using what we call a one data library/multiple code approach; for this purpose we invited many codes to submit results using the ENDF/B-VII.0 data; the most detailed results presented in this report compare MCNP and TART. The bottom line is that we have shown that using the new ENDF/B-VII.0 data library with a variety of transport codes, for the first time we are able to reproduce the expected K-eff values for all three assemblies to within the quoted accuracy of the models, namely 1.0 +/- 0.001. This is a BIG improvement compared to the results obtained using the older ENDF/B-VI.8 data library. Another important result of this study is that we have demonstrated that currently there are many computer codes that can accurately use the new ENDF/B-VII.0 data.
Date: July 27, 2007
Creator: Cullen, D E; Blomquist, R N; Brown, P N; Dean, C J; Dunn, M E; Lee, Y et al.
Partner: UNT Libraries Government Documents Department