Experimental results from pressure testing a 1:6-scale nuclear power plant containment

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Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, For sale by the U.S. G.P.O., Supt. of Docs. , Washington, DC
Nuclear reactors -- Containment -- Testing., Nuclear pressure vessels -- Tes
Statementprepared by D.S. Horschel.
ContributionsU.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering., Sandia National Laboratories.
The Physical Object
FormatMicroform
Paginationxii, 98, [41] p.
ID Numbers
Open LibraryOL14665727M

The test data recorded strains and deformations of the containment shell, as well as the leakage of the containment. Experimental Results from Pressure Testing A Scale Nuclear Power Plant Containment.

| National Technical Reports Library - NTIS. This report discusses the testing of a scale, reinforced-concrete containment building at Sandia National Laboratories, in Albuquerque, New Mexico. The scale-model, Light Water Reactor (LWR) containment building was designed and built to the American Society of Mechanical Engineers (ASME) code by United Engineers and Constructors, Inc., and was instrumented with over transducers to prepare for the test.

Experimental results from pressure testing a scale nuclear power plant containment [microform]. Division of Engineering. & Sandia National Laboratories.

Experimental results from pressure testing a 1: 6-scale nuclear power plant containment [microform] / prepared by D.S. Horschel Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission: For sale by the U.S.

Description Experimental results from pressure testing a 1:6-scale nuclear power plant containment FB2

G.P.O., Supt. of Docs Washington, DC. Horschel, D.S., Experimental Results from Pressure Testing of a Scale Nuclear Power Plant Containment. Technical Report No.

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NU-REG/CR, SAND, Nuclear Regulatory Commission, Washington DC, USA; Sandia National Laboratories, Albuquerque, by: 3. The paper presents the results of the determination from vibration tests of impedance functions for a concrete basemat of a one-quarter scale model of a nuclear power-plant containment building.

Seventh Int. Conf. on Structural Mechanics in Reactor Technology, Volume J6/4, Chicago, IL (August ). [4] D.S. Horschel, Experimental results from pressure test- ing a scale nuclear power plant containment, NUREG/CR, 5AND, Sandia National Lab- oratories, Albuquerque, NM ().

[5]. Horschel DS () Experimental results from pressure testing of a scale nuclear power plant containment. Technical Report No. NUREG/CR, SAND, Nuclear Regulatory Commission, Washington, DC, USA.

Horschel, D.S., Experimental Results from Pressure Testing of a Scale Nuclear Power Plant Containment. Technical Report No. NU-REG/CR, SAND, Nuclear Regulatory Commission, Washington DC, USA; Sandia National Laboratories, Albuquerque, USA.

Reactor containment of a nuclear power plant is a structure to ensure the safety of nuclear power plant. It acts as the last barrier to prevent the release of radioactive materials from NPP during accidents.

Finite element models were established to simulate a 1/3 scale model of a reactor containment building under leakage test pressure. Structural Integrity Research of the Electric Power Research Institute presents the result of the mission of the Electric Power Research Institute to conduct research and development promoting the clean, safe, and economical generation of power by the utility industry.

This book covers nuclear plant design, licensing, and regulation questions. It is well known that the y + value has a large influence on boundary layer flow predictions.

In order to investigate the influence of the y + value on the three turbulence models, nine different grids were used to model the experimental tube. The results of the calculations with different grids and the three turbulence models are shown in Fig.

figure shows the ratio of the condensation. Horschel, D.S., Experimental Results from Pressure Testing of a Scale Nuclear Power Plant Containment. Technical Report No. NU-REG/CR, SAND, Nuclear Regulatory Commission, Washington DC, USA; Sandia National Laboratories, Albuquerque, USA.

Google Scholar. The PACE experimental project is an intermediate sized experiment to investigate the behaviour of a curved specimen which is representative for the prestressed containment of a MWe nuclear power plant. The specimen is loaded by air pressure simulating the internal pressure within the reactor containment under inspection and accidental.

The AAPR reference accident is the rupture of a pipe in the primary circuit of a nuclear plant. In this case, the pressure and temperature can reach 5 bar and °C in 20 seconds.

The national project ‘Non-destructive testing of the containment structures of nuclear plants’ aims at studying the non-destructive techniques capable to.

This paper presents results of experimental investigations on spherical and cylindrical flame propagation in pre-mixed H2/air-mixtures in unconfined and semi-confined geometries. Nuclear Power. The calculated results support the applicability of the code for predicting in-containment thermal-hydraulic and aerosol phenomena during a severe accident in a nuclear power plant.

Abstract. Nuclear containment structure is one of the most important infrastructure systems ensuring the safety of a nuclear power plant.

In this paper, the structural behavior of cylindrical concrete containment structure was investigated using two 1/scaled nuclear containment specimens subjected to reversed cyclic loadings. The SL-1, or Stationary Low-Power Reactor Number One, was a United States Army experimental nuclear power reactor in the United States that underwent a steam explosion and meltdown on January 3,killing its three operators.

The direct cause was the improper withdrawal of the central control rod, responsible for absorbing neutrons in the reactor core.

The Moody and Henry–Fauske critical flow models implemented in Advanced Process Simulation Software (apros) have been validated against Marviken critical flow experiments and compared with other available simulations of the same models in combination with discharge coefficient (suggested for best estimate calculations) produce results close to the experimental.

High Energy Line Breaks (HELBs) inside nuclear reactor containment are recognized as challenges to Pressurized Water Reactor (PWR) and Boiling Water Reactor (BWR) nuclear power plants arising from the collateral damage due to insulation, fireproofing, coatings, and other miscellaneous materials which are shredded and transported during the event.

As part of EDF's continuous effort for the management of Long Term Operation (LTO) of its fleet of Nuclear Power Plants, an experimental mock-up of a reactor containment-building at 1/3 scale has.

Nuclear Research and Consultancy Group (NRG), PO ZG Petten, The Netherlands Received 16 October ; received in revised form 23 January ; accepted 12 February Abstract In order to determine the risk associated with the presence of hydrogen in a nuclear power plant containment during a hypothetical severe.

Containment – Shippingport Nuclear Power Plant – 10 Appendix A: General Design Criteria Containment Integrity Research Quarter-scale containment is the largest and most comprehensively instrumented scaled nuclear reactor containment vessel model ever tested.

Finite Element Model – 3D Shell Response. CAP is a large passive pressurized water reactor nuclear power plant, which relies on engineering safety features such as passive containment cooling system (PCS) to remove the decay heat in the containment and mitigate accident consequences.

Experimental Results from Pressure Testing of a Scale Nuclear Power Plant Containment. Technical Report No. NU-REG/CR, SAND, Nuclear Regulatory Commission, Washington DC, USA; Sandia National Laboratories, Albuquerque, USA.

Details Experimental results from pressure testing a 1:6-scale nuclear power plant containment EPUB

A molten salt loop will use piping of 1/5 the diameter, and pumps 1/20 the power, of those required for high-pressure helium, while staying at atmospheric pressure Smaller, low pressure containment.

By using liquid salt as the coolant instead of pressurized water, a containment structure only slightly bigger than the reactor vessel can be used. Experimental results from pressure testing a scale nuclear power plant containment Technical Report Horschel, D.

This report discusses the testing of a scale, reinforced-concrete containment building at Sandia National Laboratories, in Albuquerque, New Mexico. The Containment Technology Test Facility (CTTF) and the Surtsey Test Facility at Sandia National Laboratories are used to perform scaled experiments for the Nuclear Regulatory Commission that simulate high pressure melt ejection (HPME) accidents in a nuclear power plant (NPP).

These. Allen et al., "Experiments to Investigate Direct Containment Heating Phenomena with Scaled Models of the Zion Nuclear Plant in the Surtsey Test Facility", NUREGKR-SAND, Sandia National Laboratories, May J.

Binder, L. McUmber, and B. Spencer, "Direct Containment Heating Integral Effects Tests at 1/40 Scale in Zion Nuclear Power Plant Geometry,".

Tn the framework of the PTA-ENDE project, a 1/3 model of a preconstrained concrete containment (EDF VeRCoRs mock-up) is placed under pressure to study the leakage of the structure. During this evaluation protocol, specific areas are monitored by the NCWT (during 5 days, which correspond to the protocol of nuclear power plant pressurization.A nuclear meltdown (core meltdown, core melt accident, meltdown or partial core melt) is a severe nuclear reactor accident that results in core damage from overheating.

The term nuclear meltdown is not officially defined by the International Atomic Energy Agency or by the Nuclear Regulatory Commission. It has been defined to mean the accidental melting of the core of a nuclear reactor.

This article is based on material summarized and excerpted from Chapter 9, pages of the author’s book, Maintenance Process Instrumentation in Nuclear Power Plants .