Showing papers in "Nuclear Engineering and Design in 1969"

TL;DR: In this paper, the idea of finite element discretisation is applied to time dependent dynamic phenomena, where the time is discretised into a set of finite elements which are taken to be the same for all structural elements.

TL;DR: In this article, graphite behavior under Molten Salt Breeder Reactor (MSBR) conditions is reviewed and its influence on MSBR performance is estimated, based on the irradiation behavior of small-sized graphite specimens, a permissible reactor exposure for MSBR graphite is about 3 × 1022 neutrons/cm2 (E > 50 keV).

TL;DR: In this paper, the authors formulate finite element models for the analysis of nonlinear problems in the dynamical theory of coupled thermoelasticity, where displacement and temperature fields are approximated over a finite element, and energy balances are formed which lead to general equations of heat conduction and motion of finite elements.

TL;DR: In this article, the authors reported on static deflections and flutter-like vibrations in flat-plate nuclear reactor fuel assemblies and explained why a support comb at the leading edge is an effective means to prevent flutter.

TL;DR: Automatic System of Kinematic Analysis (ASKA) as discussed by the authors implements the matrix displacement method, using a discretisation technique, and the complete system is idealised into an assembly of finite elements to which a simplified strain pattern is ascribed.

TL;DR: In this paper, the properties of carbon and low-alloy steels currently used in the USA for commercial nuclear power reactor pressure vessel construction are examined in reference to higher strength-higher alloy steels having potential for advanced reactor service.

TL;DR: In this paper, a discussion of studies on volume increase phenomena observed in highly irradiated austenitic stainless steels is given, which are related to the production of polyhedral cavities.

TL;DR: In this paper, an analytical method to estimate coastdown behavior in indirect cycle water-cooled reactor systems is described. But this method is applicable to a system with one reactor and any number of centrifugal pumps.

TL;DR: Theoretical predictions and experimental results are compared for both close and wide spacings as mentioned in this paper, and current thinking on the following topics are also presented: (a) circumferential variation of rod temperature, (b) effect of rod displacement on its average heat transfer coefficient and on those of its six neighbors, effect of pitch: diameter ratio on the rod-average heat transfer coefficients, and (d) the interrelated problems of wetting, oxides, and gas entrainment.

TL;DR: In this paper, an analysis of heat transfer in infinite triangular or rectangular arrays of fuel rods cooled by a liquid metal in turbulent axial flow is presented, which involves the simultaneous solution of the heat conduction equations for fuel, bond, cladding and coolant.

TL;DR: In this paper, a sample calculation is given for the concrete tested at the Oak Ridge National laboratory (USA) Tower Shielding Facility (TFL) and the parameters for these formulas were calculated from recent cross sections.

TL;DR: In this paper, the vapor pressure, composition, compressibility factor, specific heat and specific heat ratio of liquid metal vapors under saturated and superheated conditions were calculated by kinetic theory up to 3000°K.

TL;DR: A series of thermo-hydraulic model tests were carried out to confirm that the first nuclear ship reactor in Japan was properly designed as mentioned in this paper, and the measured results were compared with the design calculation of the reactor.

TL;DR: In this paper, a method developed for time dependent stress analysis of prestressed concrete pressure vessels is described, where the time is divided into short intervals during which the stresses are supposed to remain constant.

TL;DR: The guarantee of safety in the Japan nuclear ship is a dominant design criterion; this means: not-to-sink, anticollision, anti-grounding, good steering apparatus, fire protection, auxiliary propulsion and safe reactor control under all conceivable ship motions and in cases of malfunctioning of auxiliary equipments as discussed by the authors.

TL;DR: In this article, the surface-type neutron moisture gauge has been simulated with a modified version of the 05R Monte Carlo code available from the Radiation Shielding Information Center at Oak Ridge, Tennessee.

TL;DR: In this article, the quenching of a sphere with a uniform time dependent heat transfer coefficient and the response of a constant uniform heat source to a changing heat transfer coefficients are formulated as integral equations for the surface temperature histories.

TL;DR: In this paper, a simple model which represents the behavior of the cladding when subjected to the imposed loading is established, and the equations pertinent to the solution of the problem are presented for the case when the material creep law is of the form ϵ = K(σ − σ 0 ).

TL;DR: In this paper, the design criteria of the PCRV cavity liner and the penetration liners and closures are discussed, including the requirements for anchoring the liners to the concrete and the closure design requirements.

TL;DR: An extensive survey of linear elastic analysis methods for one-, two-, and three-dimensional continua is presented in this article, where the basic variation principles, significant for the development and understanding of the fundamentals of the structural analysis are given, and their use in deriving the basic equations is demonstrated.

TL;DR: In this paper, the classical theory of thermoelasticity for infinitesimal displacements was used to study the stresses and displacements caused by heat generation in infinite single or multiple flat plates.

TL;DR: The Radiation Shielding Information Center (RSIC) at Oak Ridge National Laboratory, Oak Ridge, Tennessee, USA, is a technical institute serving the international scientific community as mentioned in this paper, which serves those engaged in research and development for the design of shields that provide protection from biological and physical damage due to penetrating, ionizing radiation.

TL;DR: In this article, a straighforward procedure for calculating the radial and tangential stresses in a prestressed concrete cylindrical section is described and illustrated, and a comparison with more sophisticated procedures is presented.

TL;DR: In this paper, the authors developed models for composite fuel element behavior that are based on end-of-life performance (FIGRO), steady-state behavior (DEFORM), and pseudo-transient behavior (CYGRO), and incorporated some of the proposed swelling models into their methods of evaluating fuel element performance.

TL;DR: In this paper, scale models of salt pillars and their surrounding rooms have been fabricated from cores taken in mines at Lyons and Hutchinson, Kansas; Retsof, New York; Detroit, Michigan; Grand Saline, Texas; Cote Blanche, Louisiana; and Asse, Germany.

TL;DR: In this article, a simplified analysis of buoyancy and viscous forces is given to show the method of correlating the temperature data, and experimental results have good correlation when presented according to the analysis.

TL;DR: The U.S. Army's Office of Civil Defense recently installed a device for precise calibration of gamma radiation detection instruments as discussed by the authors, which will be the primary standard for a nationwide radiobiological instrument maintenance and calibration program.

TL;DR: In this article, specific structural design criteria for a primary containment structure from the characteristics of a power reactor system were formulated and compared to the criteria used in the United States. But the focus was on limit design evaluations and their significance as they pertain to predefined failure conditions.