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Analysis of LOFT steam generator main feed piping loop seal modification

Description: The stress analysis is presented for the proposed loop seal modification to the LOFT Steam Generator Main Feed Piping. THE SAP IV finite element computer program was used to analyze normal, upset, emergency, and faulted conditions. Results of the analysis indicate that the modified main feed piping system will satisfy all structural adequacy criteria specified in Subarticle NC-3650 of the ASME Boiler and Pressure Vessel Code. Results also show that the isolation snubber configuration, specified… more
Date: February 14, 1978
Creator: Nitzel, M.E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

PWR blowdown heat transfer separate-effects program: thermal-hydraulic test facility experimental data report for test 104

Description: Reduced instrument responses are presented for Thermal-Hydraulic Test Facility (THTF) test 104, which is part of the ORNL Pressurized-Water Reactor (PWR) Blowdown Heat Transfer Separate-Effects Program. The objective of the program is to investigate the thermal-hydraulic phenomenon governing the energy transfer and transport processes that occur during a loss-of-coolant accident in the PWR system. Test 104 was conducted to obtain CHF in bundle 1 under blowdown conditions. The primary purpose of… more
Date: February 14, 1978
Creator: Leon, D. M.; White, M. D.; Moore, P. A. & Hedrick, R. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

LOFT blowdown loop piping thermal analysis Class I review

Description: In accordance with ASME Code, Section III requirements, all analyses of Class I components must be independently reviewed. Since the LOFT blowdown loop piping up through the blowdown valve is a Class I piping system, the thermal analyses are reviewed. The Thermal Analysis Branch comments to this review are also included. It is the opinion of the Thermal Analysis Branch that these comments satisfy all of the reviewers questions and that the analyses should stand as is, without additional conside… more
Date: February 14, 1978
Creator: Kinnaman, T.L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Flooding Experiments and Modeling for Improved Reactor Safety

Description: Countercurrent two-phase flow and “flooding” phenomena in light water reactor systems are being investigated experimentally and analytically to improve reactor safety of current and future reactors. The aspects that will be better clarified are the effects of condensation and tube inclination on flooding in large diameter tubes. The current project aims to improve the level of understanding of flooding mechanisms and to develop an analysis model for more accurate evaluations of flooding in the … more
Date: September 14, 2008
Creator: Solmos, M., Hogan, K.J., VIerow, K.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

A Multivariate Time Series Method for Monte Carlo Reactor Analysis

Description: A robust multivariate time series method has been established for the Monte Carlo calculation of neutron multiplication problems. The method is termed Coarse Mesh Projection Method (CMPM) and can be implemented using the coarse statistical bins for acquisition of nuclear fission source data. A novel aspect of CMPM is the combination of the general technical principle of projection pursuit in the signal processing discipline and the neutron multiplication eigenvalue problem in the nuclear engine… more
Date: August 14, 2008
Creator: Ueki, Taro
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Capability of LOFT vital batteries to supply emergency power demands during severe cold weather conditions

Description: This study evaluates the capability of the vital batteries (PPS) to provide electrical power via the vital DC-AC motor generator sets to the LOFT PPS loads during severe cold weather conditions. It is concluded that these batteries while at a temperature of 5/sup 0/F will supply the necessary PPS electrical loads for a time in excess of the one hour permitted to start the diesel generators and are, therefore, adequate at this temperature. This Revision B of the LTR includes revised, more recent… more
Date: November 14, 1978
Creator: Yeates, J. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Analog program in reactor speed of control studies

Description: One of the characteristics of the safety control system of the Hanford reactors which is of primary concern from the standpoint of reactor safety is the response time. The purpose of this study is to determine whether the safety control system is sufficiently fast-acting to prevent an intolerably large power excursion from developing. An intolerably large power excursion is one that would cause a melting of the uranium while the reactor power is above the previous operating level. The purpose o… more
Date: June 14, 1961
Creator: Cameron, W. D. & Tiller, R. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Surge Nozzle NDE Specimen Mechanical Stress Improvement Analysis

Description: The purpose of this project was to perform a finite element analysis of a pressurized water reactor pressurizer surge nozzle mock-up to predict both the weld residual stresses created in its construction and the final stress state after the application of the Mechanical Stress Improvement Process (MSIP). Strain gages were applied to the inner diameter of the mock-up to record strain changes during the MSIP. These strain readings were used in an attempt to calculate the final stress state of the… more
Date: July 14, 2011
Creator: Fredette, Lee F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Criticality Model

Description: The ''Disposal Criticality Analysis Methodology Topical Report'' (YMP 2003) presents the methodology for evaluating potential criticality situations in the monitored geologic repository. As stated in the referenced Topical Report, the detailed methodology for performing the disposal criticality analyses will be documented in model reports. Many of the models developed in support of the Topical Report differ from the definition of models as given in the Office of Civilian Radioactive Waste Manag… more
Date: September 14, 2004
Creator: Alsaed, A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Offsite exposure from failure of waste gas processing system piping failure

Description: A calculation has been performed to determine the offsite exposure to the general public in the unlikely event of the failure of Waste Gas Processing System (WGPS) piping. The consequences for this type of accident are limited by DOEM 0524 with an offsite dose of 1.5 REM. As can be seen in this LTR, the doses from this accident are far in excess of the 0524 limits. Also included in this LTR is a calculation of the BST gas space contents vs. time in the event of a WGPS piping failure.
Date: September 14, 1978
Creator: Swartzwelder, R.B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

University Reactor Matching Grants Program

Description: During the 2002 Fiscal year, funds from the DOE matching grant program, along with matching funds from the industrial sponsors, have been used to support research in the area of thermal-hydraulics. Both experimental and numerical research projects have been performed. Experimental research focused on two areas: (1) Identification of the root cause mechanism for axial offset anomaly in pressurized water reactors under prototypical reactor conditions, and (2) Fluid dynamic aspects of thin liquid … more
Date: February 14, 2003
Creator: Valentine, John; Rahnema, Farzad & Abdel-Khalik, Said
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Stress analysis of LOFT containment vessel attachments for the mainsteam and feedwater piping support structures

Description: The LOFT Containment Vessel attachments for the Mainsteam and Feedwater Piping Support Structures have been analyzed for operating and faulted loading conditions. This report contains the analysis of the connections to the containment vessel for the most current design and loading. Also contained in this report is the analysis of the piping supports.
Date: September 14, 1977
Creator: Finicle, D. P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

SENSITIVITY STUDIES FOR THE PWR ROD EJECTION ACCIDENT

Description: The objective of this study was to understand the uncertainty in fuel enthalpy calculated for the rod ejection accident (REA) in a pressurized water reactor (PWR). This is to help the US Nuclear Regulatory Commission in making judgments about acceptance criteria for the REA when high burnup fuel is used and for assessing the validity of licensee methods for calculating the REA. The approach is twofold. Sensitivity studies were first done to determine the effect on calculated fuel enthalpy of un… more
Date: November 14, 1999
Creator: Diamond, David J.; Yang, Chae-Yong & Aronson, Arnold L.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Characteristics of hydride precipitation and reorientation in spent-fuel cladding.

Description: The morphology, number density, orientation, distribution, and crystallographic aspects of Zr hydrides in Zircaloy fuel cladding play important roles in fuel performance during all phases before and after discharge from the reactor, i.e., during normal operation, transient and accident situations in the reactor, temporary storage in a dry cask, and permanent storage in a waste repository. In the past, partly because of experimental difficulties, hydriding behavior in irradiated fuel cladding ha… more
Date: November 14, 2000
Creator: Chung, H. M.; Strain, R. V. & Billone, M. C.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Corrosion Tests of LWR Fuels - Nuclide Release

Description: Two BWR fuels [64 and 71 (MWd)/kgU], one of which contained 2% Gd, and two PWR fuels [30 and 45 (MWd)/kgU], are tested by dripping groundwater on the fuels under oxidizing and hydrologically unsaturated conditions for times ranging from 2.4 to 8.2 yr at 90 C. The {sup 99}Tc, {sup 129}I, {sup 137}Cs, {sup 97}Mo, and {sup 90}Sr releases are presented to show the effects of long reaction times and of gadolinium on nuclide release. This investigation showed that the five nuclides at long reaction t… more
Date: December 14, 2001
Creator: Finn, P.A.; Tsai, Y. & Cunnane, J.C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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