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in subjects: "Reactor Vessels"  
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Robotics and Automation Activities at the Savannah River Site: A Site Report for SUBWOG 39F

Description: The Savannah River Site has successfully used robots, teleoperators, and remote video to reduce exposure to ionizing radiation, improve worker safety, and improve the quality of operations. Previous reports have described the use of mobile teleoperators in coping with a high level liquid waste spill, the removal of highly contaminated equipment, and the inspection of nuclear reactor vessels. This report will cover recent applications at the Savannah River, as well as systems which SRS has deliv… more
Date: September 28, 1995
Creator: Teese, G.D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Heavy-section steel irradiation program. Progress report, October 1994--March 1995

Description: This document is the October 1994-March 1995 Progress Report for the Heavy Section Steel Irradiation Program. The report contains a summary of activities in each of the 14 tasks of the HSSI Program, including: (1) Program management, (2) Fracture toughness shifts in high-copper weldments, (3) Fracture toughness shifts in low upper-shelf welds, (4) Irradiation effects in a commercial low upper-shelf weld, (5) Irradiation effects on weld heat-affected zone and plate materials, (6) Annealing effec… more
Date: October 1, 1995
Creator: Corwin, W. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Observations of the boiling process from a downward-facing torispherical surface: Confirmatory testing of the heavy water new production reactor flooded cavity design

Description: Reactor-scale ex-vessel boiling experiments were performed in the CYBL facility at Sandia National Laboratories. The boiling flow pattern outside the RPV bottom head shows a center pulsating region and an outer steady two-phase boundary layer region. The local heat transfer data can be correlated in terms of a modified Rohsenow correlation.
Date: June 1, 1995
Creator: Chu, T. Y.; Bentz, J. H. & Simpson, R. B.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Biaxial loading effects on fracture toughness of reactor pressure vessel steel

Description: The preliminary phases of a program to develop and evaluate fracture methodologies for assessing crack-tip constraint effects on fracture toughness of reactor pressure vessel (RPV) steels have been completed by the Heavy-Section Steel Technology (HSST) Program. Objectives were to investigate effect of biaxial loading on fracture toughness, quantify this effect through existing stress-based, dual-parameter, fracture-toughness correlations, or propose and verify alternate correlations. A crucifor… more
Date: March 1, 1995
Creator: McAfee, W. J.; Bass, B. R.; Bryson, J. W., Jr. & Pennell, W. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

An interim report on shallow-flaw fracture technology development

Description: Shallow-flaw fracture technology is being developed for application to the safety assessment of radiation-embrittled nuclear reactor pressure vessels (RPVS) containing flaws. Fracture mechanics tests on RPV steel, coupled with detailed elastic-plastic finite-element analyses of the crack-tip stress fields, have shown that (1) constraint relaxation at the crack tip of shallow surface flaws results in increased data scatter but no increase in the lower-bound fracture toughness, (2) the nil ductil… more
Date: June 1, 1995
Creator: Pennell, William E.; Bass, B. Richard; Bryson, John W. & McAfee, Wallace J.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Application of NUREG/CR-5999 interim fatigue curves to selected nuclear power plant components

Description: Recent test data indicate that the effects of the light water reactor (LWR) environment could significantly reduce the fatigue resistance of materials used in the reactor coolant pressure boundary components of operating nuclear power plants. Argonne National Laboratory has developed interim fatigue curves based on test data simulating LWR conditions, and published them in NUREG/CR-5999. In order to assess the significance of these interim fatigue curves, fatigue evaluations of a sample of the … more
Date: March 1995
Creator: Ware, A. G.; Morton, D. K. & Nitzel, M. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

105 K-West isolation barrier leak recovery plan

Description: Leak testing is being performed in 105 KW to verify the performance of the isolation barriers which have been recently installed. When an 11 inch differential head is established between the main basin and the discharge chute, a leak-rate of approximately 30 - 35 gpm is observed. The leak-rate would be achieved by a 1.65`` - 2`` diameter hole (or equivalent). Analyses suggest that the flow is turbulent/laminar transitional (dominantly turbulent), which would be indicative of a single point leak… more
Date: March 2, 1995
Creator: Wiborg, J.C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Fracture behavior of shallow cracks in full-thickness clad beams from an RPV wall section

Description: A testing program is described that utilizes full-thickness clad beam specimens to quantify fracture toughness for shallow cracks in weld material for which metallurgical conditions are prototypic of those found in reactor pressure vessels (RPVs). The beam specimens are fabricated from an RPV shell segment that includes weld, plate and clad material. Metallurgical factors potentially influencing fracture toughness for shallow cracks in the beam specimens include material gradients and material … more
Date: April 1, 1995
Creator: Keeney, J. A.; Bass, B. R. & McAfee, W. J.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Heavy-section steel irradiation program. Semiannual progress report, September 1993--March 1994

Description: Maintaining the integrity of the reactor pressure vessel (RPV) in a light-water-cooled nuclear power plant is crucial in preventing and controlling severe accidents that have the potential for major contamination release. The RPV is the only component in the primary pressure boundary for which, if it should rupture, the engineering safety systems cannot assure protection from core damage. It is therefore imperative to understand and be able to predict the capabilities and limitations of the int… more
Date: April 1995
Creator: Corwin, W.R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Advanced neutron source materials surveillance program

Description: The Advanced Neutron Source (ANS) will be composed of several different materials, one of which is 6061-T6 aluminum. Among other components, the reflector vessel and the core pressure boundary tube (CPBT), are to be made of 6061-T6 aluminum. These components will be subjected to high thermal neutron fluences and will require a surveillance program to monitor the strength and fracture toughness of the 6061-T6 aluminum over their lifetimes. The purpose of this paper is to explain the steps that w… more
Date: January 1, 1995
Creator: Heavilin, S.M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Effect of long-term thermal aging on the fracture toughness of austenitic stainless steel base and weld metals

Description: Compact tension specimens taken from FFTF primary piping materials (Type 316 stainless steel (SS) and 16-8-2 SS weld metal) and from reactor vessel materials (304 SS and 308 SS weld metal) were heated in laboratory furnaces from 100,000 hours. Fracture toughness testing was performed on these specimens, which are 7.62- and 25.4-mm thick, respectively at the aging temperature (482 and 427 degrees). Results were analyzed with the multiple-specimen method. Thermal aging continues to reduce the fra… more
Date: September 27, 1995
Creator: Huang, F.F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Dynamic response of the high flux isotope reactor structure caused by nearby heavy load drop

Description: A heavy load of 50,000 lb is assumed to drop from 10 ft above the bottom of the High Flux Isotope Reactor (HFIR) pool at the loading station. The consequences of the dynamic impact to the bottom slab of the pool and to the nearby HFIR reactor vessel are analyzed by applying the ABAQUS computer code The results show that both the BM vessel structure and its supporting legs are subjected to elastic disturbances only and, therefore, will not be damaged. The bottom slab of the pool, however, will b… more
Date: September 1, 1995
Creator: Chang, Shih-Jung
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Microstructural Investigations of as-Fabricated, Long-Term Thermally Aged and Neutron Irradiated RPV Materials: An Atom Probe Study

Description: Atom probe field ton microscopy (APFIM) investigations of the microstructure of as-fabricated, long-term thermally aged ({approximately}100,000h. at 540{degrees}F (282{degrees}C)) and neutron-irradiated (6.6{times}10{sup 18} and 3.47{times}10{sup 19} n cm{sup {minus}2} (E>1 MeV) at {approximately}550{degrees}F (288{degrees}C)) surveillance materials from commercial reactor pressure vessel steels were performed This combination of materials and conditions permitted the investigation of potential… more
Date: September 1995
Creator: Pareige, P. J.; Miller, M. K. & Stoller, R. E.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

The method of life extension for the High Flux Isotope Reactor vessel

Description: The state of the vessel steel embrittlement as a result of neutron irradiation can be measured by its increase in the nil ductility temperature (NDT). This temperature is sometimes referred to as the brittle-ductile transition temperature (DBT) for fracture. The life extension of the High Flux Isotope Reactor (HFIR) vessel is calculated by using the method of fracture mechanics. A hydrostatic pressure test (hydrotest) is performed in order to determine a safe vessel static pressure. It is then … more
Date: August 1, 1995
Creator: Chang, Shib-Jung
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Analytical modeling of the effect of crack depth, specimen size, and biaxial stress on the fracture toughness of reactor vessel steels

Description: Fracture, toughness values for A533-B reactor pressure vessel (RPV) steel obtained from test programs at Oak Ridge National Laboratory (ORNL) and University of Kansas (KU) are interpreted using the J-A{sub 2} analytical model. The analytical model is based on the critical stress concept and takes into consideration the constraint effect using the second parameter A{sub 2} in addition to the generally accepted first parameter J which represents the loading level. It is demonstrated that with the… more
Date: February 1, 1995
Creator: Chao, Yuh-Jin & Lam, Poh-Sang
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Reactor pressure vessel integrity research at the Oak Ridge National Laboratory

Description: Maintaining the integrity of the reactor pressure vessel (RPV) in a light-water-cooled nuclear power plant is crucial in preventing and controlling severe accidents that have the potential for major contamination release. The RPV is the only key safety-related component of the plant for which a duplicate or redundant backup system does not exist. It is therefore imperative to understand and be able to predict the integrity inherent in the RPV. For this reason, the U.S. Nuclear Regulatory Commis… more
Date: December 31, 1995
Creator: Corwin, W.R.; Pennell, W.E. & Pace, J.V.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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