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in subjects: "Pressure Vessels"

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Integrity of PWR pressure vessels during overcooling accidents

The reactor pressure vessel in a pressurized water reactor is normally subjected to temperatures and pressures that preclude propagation of sharp, crack-like defects that might exist in the wall of the vessel. However, there is a class of postulated accidents, referred to as overcooling accidents, that can subject the pressure vessel to severe thermal shock while the pressure is substantial. As a result of such accidents vessels containing high concentrations of copper and nickel, which enhance… more

Date: January 1, 1982

Creator: Cheverton, R.D.; Iskander, S.K. & Whitman, G.D.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Coal Technology Program. Progress report for November 1977

A block of Pittsburgh seam bituminous coal and a block of Wyodak subbituminous coal were pyrolyzed under reducing gas in support of in situ gasification. Information from previously completed block pyrolysis of bituminous coal under an argon atmosphere show that differences in evolved gas result from differences in heating rates. Compared to block pyrolysis at 0.3 C/sup 0//min, block pyrolysis at 3 C/sup 0//min produces less gas but gas with a higher heating value, yielding a higher overall pyr… more

Date: January 1, 1978

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Metals and Ceramics Division. Annual progress report, ending June 30, 1980

Research is reported concerning: (1) engineering materials, including materials compatibility, mechanical properties, nondestructive testing, pressure vessel technology, and welding and brazing; (2) fuels and processes consisting of ceramic technology, fuel cycle technology, fuels evaluation, fuel fabrication and metals processing; and (3) materials science which includes, ceramic studies, physical metallurgy properties, radiation effects and microstructural analysis, metastable and superconduc… more

Date: September 1, 1980

Item Type: Report

Partner: UNT Libraries Government Documents Department

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PNL technical review of pressurized thermal-shock issues. [PWR]

Pacific Northwest Laboratory (PNL) was asked to develop and recommend a regulatory position that the Nuclear Regulatory Commission (NRC) should adopt regarding the ability of reactor pressure vessels to withstand the effects of pressurized thermal shock (PTS). Licensees of eight pressurized water reactors provided NRC with estimates of remaining effective full power years before corrective actions would be required to prevent an unsafe operating condition. PNL reviewed these responses and the r… more

Date: July 1, 1982

Creator: Pedersen, L. T.; Apley, W. J.; Bian, S. H.; Defferding, L. J.; Morgenstern, M. H.; Pelto, P. J. et al.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Static and dynamic analyses on the MFTF-B vacuum vessel. Revision 1

The Mirror Fusion Test Facility is a major magnetic fusion energy project at the Lawrence Livermore National Laboratory. An important component of this facility is the vacuum vessel, which forms the vacuum chamber. The vessel is supported on twenty-two pairs of legs that rest on reinforced concrete piers. In performing static and dynamic analyses on the vacuum vessel, we separately investigated the load distribution under gravity loads, pressure loads, electromagnetic loads, and thermal loads. … more

Date: January 15, 1984

Creator: Ng, D.S.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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SM-1A PROJECT--TECHNICAL MANUAL: CHEMISTRY

A manual is given of the equipment and procedures used in the Army Reactor (SM-1A) to control the water purity and makeup. In addition to a description of the primary purification control system, a discussion is presented of the water chemistry control procedures for the auxiliary systems (e.g., the spent-fuel pit, the shield tank, and the waste disposal system). (T.F.H.)

Date: September 29, 1960

Creator: Chupak, J.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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LWR-PV damage estimate methodology

A credible estimate of the pressure vessel lifetime due to neutron-induced embrittlement is studied. The first step toward this goal is the accurate prediction of fluence and neutron energy spectrum at the pressure vessel. This, in turn, is obtained from least squares unfolding techniques of dosimetry measurements at a surveillance position, transport calculations, and a translation of information obtained at the surveillance position to the damage position. Including a prototypic neutron field… more

Date: January 1, 1980

Creator: Wagschal, J.J.; Maerker, R.E. & Broadhead, B.L.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Methods for measuring the surface tritium inside TFTR using beta decay

Three potential methods for measuring the surface tritium content of the TFTR vacuum vessel are described, each based on a different technique for measuring the in situ beta emission from tritium. These methods should be able to provide both a local and a global assessment of the tritium content within the top [approx] 1[mu]m of the inner wall surface.

Date: January 1, 1994

Creator: Zweben, S. J.; Johnson, D. & Hill, K. (Princeton Univ., NJ (United States). Plasma Physics Lab.) (and others)

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Work on surveillance dosimetry and benchmarks used for US power reactors and for irradiation experiments

No Description Available.

Date: January 1, 1991

Creator: Kam, F. B. K. & Stallmann, F. W.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

The electrical insulation of the DIII-D advanced divertor electrode

The electrode for biasing experiments on the DIII-D tokamak was installed in the summer of 1990 and biasing experiments have shown positive results. For the electrode, electrical insulation had to provide voltage standoff in the DIII-D divertor environment of neutral pressures in the range of 10{sup {minus}8} to 5 {times} 10{sup {minus}2} torr, variable magnetic fields, and in the presence of ionizing radiation. The electrical insulation system was designed and tested in air and vacuum for volt… more

Date: October 1, 1991

Creator: Smith, J. P.; Schaffer, M. J. & Hyatt, A. W.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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Reactor calculation benchmark PCA blind test results

Further improvement in calculational procedures or a combination of calculations and measurements is necessary to attain 10 to 15% (1 sigma) accuracy for neutron exposure parameters (flux greater than 0.1 MeV, flux greater than 1.0 MeV, and dpa). The calculational modeling of power reactors should be benchmarked in an actual LWR plant to provide final uncertainty estimates for end-of-life predictions and limitations for plant operations. 26 references, 14 figures, 6 tables.

Date: January 1, 1980

Creator: Kam, F.B.K. & Stallmann, F.W.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Compact nuclear power systems based on particle bed reactors

Compact, low cost nuclear power systems with an extremely low radioactive inventory are described. These systems use the Particle Bed Reactor (PBR), in which HTGR particle fuel is contained in packed beds that are changed daily. The small diameter particle fuel (500 ..mu..m) is directly cooled utilizing the large heat transfer area available (7.8 m/sup 2//liter), thus allowing high bed power densities (MW/liter).

Date: January 1, 1986

Creator: Horn, F. L.; Powell, J. R.; Steinberg, M. & Takahashi, H.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Fatigue and environmentally assisted cracking in light water reactors

Fatigue and stress corrosion cracking (SCC) for low-alloy steel used in piping and in steam generator and reactor pressure vessels have been investigated. Fatigue data were obtained on medium-sulfur-content A533-Gr B and A106-Gr B steels in high-purity (HP) deoxygenated water, in simulated pressurized water reactor water, and in air. Analytical studies focused on the behavior of carbon steels in boiling water reactor (BWR) environments. Crack-growth rates of composite fracture-mechanics specime… more

Date: March 1, 1992

Creator: Kassner, T.F.; Ruther, W.E.; Chung, H.M.; Hicks, P.D.; Hins, A.G.; Park, J.Y. et al.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Benchmark field study of deep neutron penetration

A unique benchmark neutron field has been established at the Lawrence Livermore National Laboratory (LLNL) to study deep penetration neutron transport. At LLNL, a tandem accelerator is used to generate a monoenergetic neutron source that permits investigation of deep neutron penetration under conditions that are virtually ideal to model, namely the transport of mono-energetic neutrons through a single material in a simple geometry. General features of the Lawrence Tandem (LATAN) benchmark field… more

Date: June 10, 1991

Creator: Morgan, J. F.; Sale, K. (Lawrence Livermore National Lab., CA (USA) ); Gold, R.; Roberts, J. H. & Preston, C. C. (Metrology Control Corp., Richland, WA (USA) )

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Quality assurance of PTS thermal hydraulic calculations at BNL. [Pressurized Thermal Shock]

Rapid cooling of the reactor pressure vessel at high pressure has a potential of challenging the vessel integrity. This phenomenon is called overcooling or Pressurized Thermal Shock (PTS). The Nuclear Regulatory Commission (NRC) has selected three plants representing three types of PWRs in use for detailed PTS study. Oconee-1 (B and W), Calvert Cliffs (C.E.), and H.B. Robinson (Westinghouse). The Brookhaven National Laboratory (BNL) has been requested by NRC to review and compare the input deck… more

Date: January 1, 1983

Creator: Rohatgi, U.S.; Pu, J.; Jo, J. & Saha, P.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Low alloy steels for thick wall pressure vessels. Yearly report, October 1, 1976--September 30, 1977

A summary is presented of progress during the first year of a program to modify current ferrous alloys and develop new low-alloy steels that can be field-fabricated into large-diameter, thick-walled pressure vessels for commercial coal gasifiers. Determination of design criteria for the pressure vessel steels, incorporating information gained through review of the literature and gained through interaction with industry, national laboratory personnel, and research contractors is described. Work … more

Date: January 1, 1977

Creator: Horn, R. M.; Parker, E. R. & Zackay, V. F.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Coal Technology Program. Progress report for December 1977

In the pressure vessel and piping materials work, the report, ''Assessment of Materials Technology for Gasifer and Reaction Pressure Vessels and Piping for Second Generation Commercial Coal Conversion Systems'' (ORNL-5238), has been submitted for publication and distribution. Impact and tensile teting is under way on 2/sup 1///sub 4/ cr-1 Mo steel which has received a simulated quench, temper, and postweld heat treatment. Two topical reports on coating inspection have gone to reproduction. CoCr… more

Date: February 1, 1978

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Reevaluation of ferritic steel DBTT data used in damage function analysis. [PWR; BWR]

Data used in damage function analysis of ferritic pressure vessel steels was improved in three areas: 1) errors in the fluences were corrected and all fluences renormalized on a common basis, 2) a physically realistic fluence dependence was used to extrapolate data to the desired property change level, and 3) improved a priori damage models were used to account for the energy dependence of damage. The above improvements eliminated spurious structure in the damage functions and reduced data scat… more

Date: January 1, 1979

Creator: Simons, R. L.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Coal Technology Program progress report for August 1977

The projects reported this month include those for coal conversion process development, materials engineering, alkali metal vapor topping cycles, a coal equipment test facility, a fluidized bed combustor technology test unit, engineering and support studies, process and program assistance, and environmental assessment studies. In hydrocarbonization research, material balance results from Run HC-21 confirm earlier tests with Wyodak coal, showing an oil yield of 21% based on MAF coal. In the coal… more

Date: October 1, 1977

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Constitutive relations in TRAC-P1A

The purpose of this document is to describe the basic thermal-hydraulic models and correlations that are in the TRAC-P1A code, as released in March 1979. It is divided into two parts, A and B. Part A describes the models in the three-dimensional vessel module of TRAC, whereas Part B focuses on the loop components that are treated by one-dimensional formulations. The report follows the format of the questions prepared by the Analysis Development Branch of USNRC and the questionnaire has been att… more

Date: August 1, 1980

Creator: Rohatgi, U.S. & Saha, P.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Vacuum chamber thermal protection for the APS (Advanced Photon Source)

The addition of undulators and wigglers into synchrotron storage rings created new problems in terms of protecting the integrity of the ring vacuum chamber. If the photon beam from these devices were missteered into striking an inadequately cooled section of the storage ring vacuum chamber, the structural strength might be reduced sufficiently that the vacuum envelope could be penetrated, resulting in long downtime of the storage ring. The new generation of high-energy synchrotron light sources… more

Date: January 1, 1989

Creator: Kramer, S. L.; Crosbie, E. A.; Kim, S.; Wehrle, R. & Yoon, M.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Gas-cooled reactor programs: High-Temperature Gas-Cooled Reactor Base-Technology Program. Annual progress report for period ending December 31, 1979

Progress in HTGR studies is reported in the following areas: HTGR chemistry; fueled graphite development; prestressed concrete pressure vessel development; structural materials; HTGR graphite studies; and evaluation of the pebble-bed HTR.

Date: July 1, 1980

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Holographic and acoustic emission evaluation of pressure vessels

Optical holographic interfereometry and acoustic emission monitoring were simultaneously used to evaluate two small, high pressure vessels during pressurization. The techniques provide pressure vessel designers with both quantitative information such as displacement/strain measurements and qualitative information such as flaw detection. The data from the holographic interferograms were analyzed for strain profiles. The acoustic emission signals were monitored for crack growth and vessel quality. more

Date: March 5, 1980

Creator: Boyd, D.M.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Validation of neutron-transport calculations in benchmark facilities for improved damage-fluence predictions

An accurate determination of damage fluence accumulated by reactor pressure vessels (RPV) as a function of time is essential in order to evaluate the vessel integrity for both pressurized thermal shock (PTS) transients and end-of-life considerations. The desired accuracy for neutron exposure parameters such as displacements per atom or fluence (E > 1 MeV) is of the order of 20 to 30%. However, these types of accuracies can only be obtained realistically by validation of nuclear data and calcula… more

Date: January 1, 1983

Creator: Williams, M.L.; Stallmann, F.W.; Maerker, R.E. & Kam, F.B.K.

Item Type: Article

Partner: UNT Libraries Government Documents Department