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MHTGR-Nuclear Island Engineering: Final summary report for the period November 30, 1987 through December 1, 1988

Description: This report summarizes the Modular High-Temperature Gas-Cooled Reactor (MHTGR) - Nuclear Island Engineering (NIE) design and development work performed by General Atomics (GA) for the period November 30, 1987 through December 1, 1988, under the Department of Energy (DOE) Contract AC03-88SF17367. The scope of the report includes work performed by Bechtel National Inc. (BNI), Combustion Engineering Inc. (C-E), and James Howden Company, as major subcontractors to GA.
Date: December 1, 1988
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Environmental aspects of MHTGR (Modular High-Temperature Gas-Cooled Reactor) operation

Description: The Modular High-Temperature Gas-Cooled Reactor (MHTGR) is an advanced reactor concept being developed under a cooperative program involving the US Government, the utilities and the nuclear industry. This plant design utilizes basic High Temperature Gas-Cooled Reactor (HTGR) features of ceramic fuel, helium coolant, and a graphite moderator. The MHTGR design approach leading to exceptional safety performance also leads to plant operation which is characterized by extremely low radiological emis… more
Date: September 1, 1988
Creator: Neylan, A. J.; Dilling, D. A. & Cardito, J. M.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Graphite design handbook

Description: The objectives of the Graphite Design Handbook (GDH) are to provide and maintain a single source of graphite properties and phenomenological model of mechanical behavior to be used for design of MHTGR graphite components of the Reactor System, namely, core support, permanent side reflector, hexagonal reflector elements, and prismatic fuel elements; to provide a single source of data and material models for use in MHTGR graphite component design, performance, and safety analyses; to present prop… more
Date: September 1, 1988
Creator: Ho, F.H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

The Licensing Experience of the Modular High-Temperature Gas-Cooled Reactor (MHTGR)

Description: The MHTGR is an advanced reactor concept being developed under a cooperative program involving the US Government, the nuclear industry, and the utilities. The design utilizes the basic HTGR features of ceramic fuel, helium coolant, and a graphite moderator. However, the specific size and configuration are selected to utilize the inherent characteristics of these materials to develop passive safety features that provide a significantly higher margin of safety than current generation reactors. Th… more
Date: September 1, 1988
Creator: Silady, F.A.; Cunliffe, J.C. & Walker, L.P.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Multiaxial graphite test specimen

Description: A multiaxial test program is to be conducted by Oak Ridge National Laboratory (ORNL) on the core component graphite. The objectives of the tests are to obtain failure data under uniaxial and biaxial states of stress in order to construct a failure surface in a two-dimensional stress space. These data will be used in verifying the accuracy of the maximum stress failure theory being proposed for use in designing the core graphite components. Tubular specimens are proposed to be used and are eithe… more
Date: September 1, 1988
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

MHTGR (Modular High-Temperature Gas-Cooled Reactor) design and development status

Description: The Modular High-Temperature Gas-Cooled Reactor (MHTGR) is an advanced power plant concept which has been under design definition since 1984. The design utilizes basic high-temperature gas-cooled reactor features of ceramic fuel, helium coolant and a graphite moderator which have been under development for 30 years. The geometric arrangement of the reactor vessels, the core and the heat removal components has been selected to exploit the inherent characteristics associated with high temperature… more
Date: August 1, 1988
Creator: Turner, R. F. & Neylan, A. J.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

H-451 graphite irradiation creep design model; Revision 1

Description: Available irradiation creep data on H-451 graphite area analyzed and fitted to the proposed creep model in a standard linear solid (a linear viscoelastic model). A creep equation is obtained and recommended for preliminary design use. It is found that the regression is significant and the creep equation is a good predictor. The standard error (SE) of the estimate is smaller than that used in the core graphite criteria development. This smaller SE shall be used in all future work related to crit… more
Date: July 1, 1988
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Metals design handbook

Description: This report gives an approved set of material properties over a range of environmental conditions which are sufficient to design the metallic components in the reactor system and hot duct assembly. Table 1-1 list these metallic components together with the reference design material chosen for each component. Table 1-2 summarizes the structural criteria of each metallic component taken from the component specifications. In all cases, the criteria references the ASME B&PV Code. The ASME-Code incl… more
Date: July 1, 1988
Creator: Betts, W.S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Design requirements for high-temperature metallic component materials in the US modular HTGR

Description: The modular high temperature gas-cooled reactor (MHTGR) is a 350 MW(t) second generation reactor system design which during normal operation circulates helium with a mixed mean coal and hot temperature of 260/sup 0/C (500/sup 0/C) and 690/sup 0/C (1270/sup 0/F), respectively. The design incorporates passive design features which allow the plant to be safely shutdown and cooled with no active systems or operator action being required. A key feature of this concept is the capability of the residu… more
Date: June 1, 1988
Creator: Shenoy, A. S. & Betts, W. S.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Predicted discharge plutonium isotopics for LEU [low-enriched uranium] test pebble irradiated in the AVR [Arbeitsgemeinschaft Versuchsreaktor]

Description: A Subprogram Plan related to the Arbeitsgemeinschaft Versuchsreaktor (AVR) Test Program is in place and describes cooperative work being carried out under the United States/Federal Republic of Germany (US/FRG) Implementing Agreement for Cooperation in Gas-Cooled Reactor Development. The AVR information to be provided as described in the plan will provide a basis for examining the accuracy of computational methods used for performance and safety analysis. The purpose of the cooperation is to obt… more
Date: June 1, 1988
Creator: Lane, R.K. & Lefler, W.L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Fission product plateout/liftoff/washoff test plan. Revision 1

Description: A test program is planned in the COMEDIE loop of the Commissariat a l`Energy Atomique (CEA), Grenoble, France, to generate integral test data for the validation of computer codes used to predict fission product transport and core corrosion in the Modular High Temperature Gas-Cooled Reactor (MHTGR). The inpile testing will be performed by the CEA under contract from the US Department of Energy (DOE); the contract will be administered by Oak Ridge National Laboratory (ORNL). The primary purpose o… more
Date: May 1, 1988
Creator: Acharya, R. & Hanson, D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Tritium distribution in the MHTGR

Description: The {sup 3}H production, transport and environmental release from the 350 MW(t) Modular High Temperature Gas Cooled Reactor was analyzed. The analysis was performed using a modified TRITGO computer code, plant data base from the Preliminary Safety Information Document and materials property data from the Fuel Design Data Manual, Issue F. The analysis indicates that most of the {sup 3}H produced in the reactor is retained by the fuel particles and the structural graphite elements. The single lar… more
Date: May 1, 1988
Creator: Acharya, R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Development of improved TRISO-P fuel particle P-PyC coating

Description: Low defect fuels are required for the MHTGR to meet tighter fuel performance for this reactor design (Ref. 1). Exposed heavy metal (HM) contamination levels must be reduced to {le} 1E-5 fraction. Particle coating breakage during the fuel compact fabrication process has been shown to be a major source of HM contamination in the final fuel compacts. Excessive forces are experienced by the coated fuel particles during matrix injection, which leads to coating failure. Adding a sacrificial, low Youn… more
Date: April 29, 1988
Creator: Adams, C.C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

MHTGR: New production reactor summary of experience base

Description: Worldwide interest in the Modular High-Temperature Gas-Cooled Reactor (MHTGR) stems from the capability of the system to retain the advanced fuel and thermal performance while providing unparalleled levels of safety. The small power level of the MHTGR and its passive systems give it a margin of safety not attained by other concepts being developed for power generation. This report covers the experience base for the key nuclear system, components, and processes related to the MHTGR-NPR. 9 refs.,… more
Date: March 1, 1988
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Reactor-specific spent fuel discharge projections, 1987-2020

Description: The creation of five reactor-specific spent fuel data bases that contain information on the projected amounts of spent fuel to be discharged from U.S. commercial nuclear reactors through the year 2020 is described. The data bases contain detailed spent fuel information from existing, planned, and projected pressurized water reactors (PWR) and boiling water eactors (BWR), and one existing high temperature gas reactor (HTGR). The projections are based on individual reactor information supplied by… more
Date: March 1, 1988
Creator: Walling, R. C.; Heeb, C. M. & Purcell, W. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Contain calculations of debris conditions adjacent to the BWR Mark I drywell shell during the later phases of a severe accident

Description: Best estimate CONTAIN calculations have recently been performed by the BWR Severe Accident Technology (BWRSAT) Program at Oak Ridge National Laboratory to predict the primary containment response during the later phases of an unmitigated low-pressure Short Term Station Blackout at the Peach Bottom Atomic Power Station. Debris pour conditions leaving the failed reactor vessel are taken from the results of best estimate BWRSAR analyses that are based upon an assumed metallic debris melting temper… more
Date: January 1, 1988
Creator: Hyman, C.R.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Depressurized core heatup accident scenarios in advanced modular high temperature gas cooled reactors

Description: The decay heat removal by a passive air colling system from a modular high tempeature gas cooled reactor during depressurized core heatup accident scenarios was analyzed. The effects of several design and operating parameters on the peak fuel and vessel temperatures were established. The results indicate that fuel and vessel temperatures remain well below failure levels and that significant safety margins exist in the key variables of decay heat and core thermal conductivities.
Date: January 1, 1988
Creator: Kroeger, P. G.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Economic characteristics of a smaller, simpler reactor

Description: Reduced load growth and heightened concern with economic risk has led to an expressed utility preference for smaller capacity additions. The Modular High Temperature Reactor (MHTGR) plant has been developed as a small, simple plant that has limited financial risk and is economically competitive with comparatively sized coal plants. Competitive economics is achieved by the simplifications made possible in a small MHTGR, reduction in the quantity of nuclear grade construction and design standardi… more
Date: January 1, 1988
Creator: LaBar, M. & Bowers, H.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Hypothetical air ingress scenarios in advanced modular high temperature gas cooled reactors

Description: Considering an extremely hypothetical scenario of complete cross duct failure and unlimited air supply into the reactor vessel of a modular high temperature gas cooled ractor, it is found that the potential air inflow remains limited due to the high friction pressure drop through the active core. All incoming air will be oxidized to CO and some local external burning would be temporarily possible in such a scenario. The accident would have to continue with unlimited air supply for hundreds of h… more
Date: January 1, 1988
Creator: Kroeger, P. G.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

The irradiation creep characteristics of graphite to high fluences

Description: High-temperature gas-cooled reactors (HTGR) have massive blocks of graphite with thermal and neutron-flux gradients causing high internal stresses. Thermal stresses are transient; however, stresses generated by differential growth due to neutron damage continue to increase with time. Fortunately, graphite also experiences creep under irradiation allowing relaxation of stresses to nominally safe levels. Because of complexity of irradiation creep experiments, data demonstrating this phenomenon ar… more
Date: January 1, 1988
Creator: Kennedy, C. R.; Cundy, M. & Kleist, G.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

MHTGR [modular high-temperature gas-cooled reactor] core physics validation plan

Description: This document contains the verification and validation (V&V) plan for analytical methods utilized in the nuclear design for normal and off-normal conditions within the Modular High-Temperature Gas-Cooled Reactor (MHTGR). Regulations, regulatory guides, and industry standards have been reviewed and the approach for V&V has been developed. MHTGR core physics methods are described and the status of previous V&V is summarized within this document. Additional work required to verify and … more
Date: January 1, 1988
Creator: Baxter, A. & Hackney, R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

MHTGR (Modular High-Temperature Gas-Cooled Reactor) technology development plan

Description: This paper presents the approach used to define the technology program needed to support design and licensing of a Modular High-Temperature Gas-Cooled Reactor (MHTGR). The MHTGR design depends heavily on data and information developed during the past 25 years to support large HTGR (LHTGR) designs. The technology program focuses on MHTGR-specific operating and accident conditions, and on validation of models and assumptions developed using LHTGR data. The technology program is briefly outlined, … more
Date: January 1, 1988
Creator: Homan, F.J. & Neylan, A.J.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Modular High-Temperature Gas-Cooled Reactor short term thermal response to flow and reactivity transients

Description: The analyses reported here have been conducted at the Oak Ridge National Laboratory (ORNL) for the US Nuclear Regulatory Commission's (NRC's) Division of Regulatory Applications of the Office of Nuclear Regulatory Research. The short-term thermal response of the Modular High-Temperature Gas-Cooled Reactor (MHTGR) is analyzed for a range of flow and reactivity transients. These include loss of forced circulation (LOFC) without scram, moisture ingress, spurious withdrawal of a control rod group, … more
Date: January 1, 1988
Creator: Cleveland, J.C.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

ORNL R and D on Advanced Small and Medium Power Reactors: Selected Topics

Description: From 1984-1985, ORNL studied several innovative small and medium power nuclear concepts with respect to viability. Criteria for assessment of market attractiveness were developed and are described here. Using these criteria and descriptions of selected advanced reactor concepts, and assessment of their projected market viability in the time period 2000-2010 was made. All of these selected concepts could be considered as having the potential for meeting the criteria but, in most cases, considera… more
Date: 1988~
Creator: White, James D. & Trauger, Donald B.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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