High-temperature gas-cooled reactor safety studies for the Division of Accident Evaluation. Quarterly progress report, April 1-June 30, 1985

doi:10.2172/6131151

High-temperature gas-cooled reactor safety studies for the Division of Accident Evaluation. Quarterly progress report, April 1-June 30, 1983. Volume 2

Ball, S.J. ; Cleveland, J.C. ; Harrington, R.M. ; ... January 1984

Work on postulated severe accident sequence code development and application continued both for the Fort St. Vrain and 2240-MW(t) lead plant designs. Initial experiments on high-temperature gas-cooled reactor (HTGR) fission-product release and transport were run in an existing high-temperature (> 2000/sup 0/C) graphite-resistance furnace. Initial work was done on a cooperative study of HTGR safety research needs.
High-temperature gas-cooled reactor safety studies for the Division of Accident Evaluation. Quarterly progress report, April 1-June 30, 1984. Volume 2

Ball, S.J. ; Cleveland, J.C. ; Harrington, R.M. ; ... November 1984

Modeling, code development, and accident analysis work on the modular High-Temperature Gas-Cooled Reactor (HTGR) systems concentrated on predictions of core and other system temperature histories for postulated long-term loss of forced circulation accidents both with and without system depressurization. Fission-product (FP) release experiments to investigate vapor pressure and diffusion rates through graphite were continued. Experiments with additional elements were conducted.
High-Temperature Gas-Cooled Reactor Safety studies for the Division of Accident Evaluation. Quarterly progress report, April 1-June 30, 1982

Ball, S.J. ; Clapp, N.E. Jr. ; Cleveland, J.C. ; ... January 1983

Continuing work on High-Temperature Gas-Cooled Reactor (HTGR) severe accident analyses included a study of a hypothetical large-scale release following a permanent loss-of-coolant accident at the Fort St. Vrain reactor and further development of the ORECA code for siting studies of the 2240-MW(t) cogeneration plant HTGR. Work on fission-product release and transport included investigations of alternative iodine chemistry scenarios and an analysis of the major areas of uncertainties in release predictions during severe accidents. Code development work showed further progress in steam generator modeling, development of a multiloop HTGR simulation, and testing of an alternative simplified core model. 5 figures.
High-Temperature Gas-Cooled Reactor safety studies for the Division of Accident Evaluation. Quarterly progress report, July 1-September 30, 1985. Volume 3

Ball, S.J. ; Cleveland, J.C. ; Conklin, J.C. ; ... April 1986

Further accident scenario analyses were done using simulations for the modular High-Temperature Gas-Cooled Reactor (HTGR), including an uncertainty analysis of the reactor vessel axial temperatures for long-term heatup accidents. More sections of the HTGR Safety Handbook were completed. Several licensing-related tasks were completed for the Fort St. Vrain HTGR.
High-temperature gas-cooled reactor safety studies for the Division of Reactor Safety Research. Quarterly progress report, April 1--June 30, 1978

Ball, S.J. ; Cleveland, J.C. ; Conklin, J.C. ; ... September 1978

Assistance was provided to NRC in evaluating and confirming ECCS analyses for the Fort St. Vrain (FSV) reactor in support of a 100% power license application. Comparisons of ORNL accident analyses with those of the applicant were generally in good agreement. Other work included further development of the ORTAP-FSV and ORECA codes and comparisons of data from several FSV scram tests with ORECA code predictions.

Title: High-temperature gas-cooled reactor safety studies for the Division of Accident Evaluation. Quarterly progress report, April 1-June 30, 1985

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Citation Formats

High-temperature gas-cooled reactor safety studies for the Division of Accident Evaluation. Quarterly progress report, April 1-June 30, 1983. Volume 2

High-temperature gas-cooled reactor safety studies for the Division of Accident Evaluation. Quarterly progress report, April 1-June 30, 1984. Volume 2

High-Temperature Gas-Cooled Reactor Safety studies for the Division of Accident Evaluation. Quarterly progress report, April 1-June 30, 1982

High-Temperature Gas-Cooled Reactor safety studies for the Division of Accident Evaluation. Quarterly progress report, July 1-September 30, 1985. Volume 3

High-temperature gas-cooled reactor safety studies for the Division of Reactor Safety Research. Quarterly progress report, April 1--June 30, 1978