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Reactor Safety Bibliography. Selected Unclassified References

Description: This is a revision of the Reactor Safety Bibliography prepared for the Reactor Safety Conference held at New York City on Oct. 31, 1957. It is not an exhaustive review of the published material on reactor safety but includes 223 selections from reports and published literature as a guide to some of the more recent and relevant material. (J.E.D.)
Date: May 1, 1957
Partner: UNT Libraries Government Documents Department

A Procedure to Determine the Relative Extent of Reactor Fission Product Releases Under Various Meteorological Conditions

Description: From Abstract and Introduction: "A procedure for the application of these programs and graphs to the review and evaluation of reactor safety problems is presented. The purpose of this work is to present of the subsequent meteorological considerations suitable for review and analysis using a small digital computer."
Date: July 1964
Creator: Lanes, Stephen J.
Partner: UNT Libraries Government Documents Department

Architectural and Algorithmic Requirements for a Next-Generation System Analysis Code

Description: This document presents high-level architectural and system requirements for a next-generation system analysis code (NGSAC) to support reactor safety decision-making by plant operators and others, especially in the context of light water reactor plant life extension. The capabilities of NGSAC will be different from those of current-generation codes, not only because computers have evolved significantly in the generations since the current paradigm was first implemented, but because the decision-making processes that need the support of next-generation codes are very different from the decision-making processes that drove the licensing and design of the current fleet of commercial nuclear power reactors. The implications of these newer decision-making processes for NGSAC requirements are discussed, and resulting top-level goals for the NGSAC are formulated. From these goals, the general architectural and system requirements for the NGSAC are derived.
Date: May 1, 2010
Creator: Mousseau, V.A.
Partner: UNT Libraries Government Documents Department

EXPERIENCE USING PHENOMENA IDENTIFICATION AND RANKING TECHNIQUE (PIRT) FOR NUCLEAR ANALYSIS.

Description: THE PHENOMENA IDENTIFICATION AND RANKING TECHNIQUE (PIRT) IS A SYSTEMATIC WAY OF GATHERING INFORMATION FROM EXPERTS ON A SPECIFIC SUBJECT, AND RANKING THE IMPORTANCE OF THE INFORMATION, IN ORDER TO MEET SOME DECISION MAKING OBJECTIVE. IT HAS BEEN APPLIED TO MANY NUCLEAR TECHONLOGY ISSUES INCLUDING NUCLEAR ANALYSIS IN ORDER TO HELP GUIDE RESEARCH OR DEVELOP REGULATORY REQUIREMENTS.
Date: June 30, 2006
Creator: DIAMOND, DAVID J.
Partner: UNT Libraries Government Documents Department

DETERMINATION OF INVENTORIES AND POWER DISTRIBUTIONS FOR THE NSBR.

Description: This memo presents the details of the methodology for developing fuel inventories for the NBSR along with power distributions predicted with this set of inventories. Several improvements have been made to the MCNP model of the NBSR since a set of calculations was performed in 2002 in support of the NBSR relicensing and SAR update. One of the most significant changes in the model was to divide the fuel elements into upper and lower halves so the effects of uneven burn between the two halves (due to the shim arms) can be determined. The present set of power distributions are provided for comparison with the previous safety analyses.
Date: September 12, 2005
Creator: HANSON, A.L. & DIAMOND, D.J.
Partner: UNT Libraries Government Documents Department

Fission product decay heat studies of December 15, 1975

Description: The purpose of the project described is to study fission product decay heating rates, with emphasis on short decay times. Isothermal calorimetry is used to perform benchmark experiments for decay times between 20 seconds and 2000 seconds with an absolute accuracy of better than 5 percent. Experiments are being done with $sup 235$U and will be done eventually with $sup 239$Pu. Thermal neutron spectra are used for the irradiations. The project was initiated in July 1974. Final results for $sup 235$U are expected by 6-30-76, and for $sup 239$Pu by 1-1-77. Final reports for each task will follow the final data by 3 months. The work done to date is described together with the status of the final experimental configuration.
Date: February 26, 1976
Creator: Yarnell, J.L. & Bendt, P.J.
Partner: UNT Libraries Government Documents Department

Coupled high fidelity thermal hydraulics and neutronics for reactor safety simulations

Description: This work is a continuation of previous work on the importance of accuracy in the simulation of nuclear reactor safety transients. This work is qualitative in nature and future work will be more quantitative. The focus of this work will be on a simplified single phase nuclear reactor primary. The transient of interest investigates the importance of accuracy related to passive (inherent) safety systems. The transient run here will be an Unprotected Loss of Flow (ULOF) transient. Here the coolant pump is turned off and the un’SCRAM’ed reactor transitions from forced to free convection (Natural circulation). Results will be presented that show the difference that the first order in time truncation physics makes on the transient. The purpose of this document is to illuminate a possible problem in traditional reactor simulation approaches. Detailed studies need to be done on each simulation code for each transient analyzed to determine if the first order truncation physics plays an important role.
Date: September 1, 2008
Creator: Mousseau, Vincent A.; Zhang, Hongbin & Zhao, Haihua
Partner: UNT Libraries Government Documents Department

Allcuts: a fast, comprehensive fault tree analysis code

Description: A description, user instructions, and a source program listing are presented for ALLCUTS, a Fortran computer code for fault tree analysis. The code was specifically designed to be easy to use as well as fast, versatile, and powerful. It may easily be modified by a moderately skilled programer to fit the variable needs of the user and the capabilities of his computer. A code, BRANCH, for determining input data gate and bottom event interrelationships is also presented. (7 references) (auth)
Date: July 1, 1975
Creator: Van Slyke, W.J. & Griffing, D.E.
Partner: UNT Libraries Government Documents Department