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PWR blowdown heat transfer separate-effects program data evaluation report: system response for thermal-hydraulic test facility test series 100

Description: Selected reduced instrument responses and analyses of the indicated phenomena are presented for Thermal-Hydraulic Test Facility (THTF) test series 100, which is part of the PWR Blowdown Heat Transfer Separate-Effects Program. The objective of the program is to investigate the thermal-hydraulic phenomena that govern the energy transfer and transport processes occurring during a postulated loss-of-coolant accident in a pressurized-water reactor system. Comparisons are made between the trends indicated by the reduced instrument responses and the thermal-hydraulic transient simulator RELAP4/MOD5 (update 2) to aid in understanding the phenomenological sequences. The results of verification studies of RELAP's performance in prediction of the THTF data are presented.
Date: October 21, 1977
Creator: Hedrick, R.A.; Craddick, W.G.; Turnage, K.G. & Hyman, C.R.
Partner: UNT Libraries Government Documents Department

Comparisons of HELIOS Calculated Isotope Concentrations to Measured Values for Several Reactor Systems

Description: Heavy metal and fission product noble gas concentrations in spent fuel from two different PWR'S were calculated using HELIOS and compared to measured results from the literature. It was found that for the U-235/U-238 and Pu-240/Pu-239 isotopic ratios, the HELIOS calculation agreed to within the experimental uncertainty. For the Xe-131/Xe-134 isotopic ratios, HELIOS tended to overestimate the result by up to 4%. Conversely for the Xe-132/Xe-134 ratios, HELIOS underestimated the result by a slight amount ({approximately}1%). This suggests that either the fission product yields for Xe-131 and Xe-132 should be slightly altered or that the absorption cross-section for Xe-131 should be slightly increased. More analysis is necessary to determine which of these two alternatives is more appropriate. This work has shown that the accuracy of HELIOS (within 2% for heavy metals and within 4% for fission noble gases) is sufficient for most analyses.
Date: October 21, 1998
Creator: Charlton, W.S.; Perry, R.T.; Fearey, B.L. & Parish, T.A.
Partner: UNT Libraries Government Documents Department

Predictions and acceptance criteria for K Reactor startup and power ascension

Description: Calculations have been performed to determine the reactivity worth of various partial rod movements to be performed in the K-14 Startup and Power Ascension Test Program. Some tests have been revised since the issuance of the predictions and acceptance criteria for the startup/power ascension testing procedure, RSP 90-007. The tests were modified to account for changes in the Technical Specifications concerning control rod positioning. This addendum describes the changes to the test configurations and documents the revised expectation values for the partial rod insertion tests. Additional calculations were performed to cover the complete range of possible full rod positions at the zero power testing level.
Date: October 21, 1991
Creator: Bond, R.A. Jr.
Partner: UNT Libraries Government Documents Department