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Title: Nuclear Island Engineering MHTGR [Modular High-Temperature Gas-cooled Reactor] preliminary and final designs. Technical progress report, December 12, 1988--September 30, 1989

Abstract

This report summarizes the Department of Energy (DOE)-funded work performed by General Atomics (GA) under the Nuclear Island Engineering (NIE)-Modular High-Temperature Gas-cooled Reactor (MHTGR) Preliminary and Final Designs Contract DE-AC03-89SF17885 for the period December 12, 1988 through September 30, 1989. This reporting period is the first (partial) fiscal year of the 5-year contract performance period. The objective of DOE`s MHTGR program is to advance the design from the conceptual design phase into preliminary design and then on to final design in support of the Nuclear Regulatory Commission`s (NRC`s) design review and approval of the MHTGR Design Team, is focused on the Nuclear Island portion of the technology and design, primarily in the areas of the reactor and internals, fuel characteristics and fuel fabrication, helium services systems, reactor protection, shutdown cooling, circulator design, and refueling system. Maintenance and implementation of the functional methodology, plant-level analysis, support for probabilistic risk assessment, quality assurance, operations, and reliability/availability assessments are included in GA`s scope of work.

Publication Date:
Research Org.:
General Atomics Co., San Diego, CA (United States)
Sponsoring Org.:
USDOE Assistant Secretary for Nuclear Energy, Washington, DC (United States)
OSTI Identifier:
453035
Report Number(s):
DOE/HTGR-88397
ON: DE97003961
DOE Contract Number:
AC03-89SF17885
Resource Type:
Technical Report
Resource Relation:
Other Information: PBD: Dec 1989
Country of Publication:
United States
Language:
English
Subject:
21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS; 22 NUCLEAR REACTOR TECHNOLOGY; HTGR TYPE REACTORS; RESEARCH PROGRAMS; PROGRESS REPORT; DESIGN; FUEL ELEMENTS; TECHNOLOGY ASSESSMENT; QUALITY ASSURANCE; REACTOR SAFETY; REACTOR SHUTDOWN; REACTOR MAINTENANCE; FABRICATION; IMPLEMENTATION; PROBABILISTIC ESTIMATION; RISK ASSESSMENT; REACTOR COOLING SYSTEMS; PERFORMANCE TESTING; DOCUMENTATION; ECONOMIC ANALYSIS; PROGRAM MANAGEMENT; REACTOR LICENSING; FISSION PRODUCTS; HEAT TRANSFER; REACTOR COMPONENTS; REACTOR CORES

Citation Formats

NONE. Nuclear Island Engineering MHTGR [Modular High-Temperature Gas-cooled Reactor] preliminary and final designs. Technical progress report, December 12, 1988--September 30, 1989. United States: N. p., 1989. Web. doi:10.2172/453035.
NONE. Nuclear Island Engineering MHTGR [Modular High-Temperature Gas-cooled Reactor] preliminary and final designs. Technical progress report, December 12, 1988--September 30, 1989. United States. doi:10.2172/453035.
NONE. 1989. "Nuclear Island Engineering MHTGR [Modular High-Temperature Gas-cooled Reactor] preliminary and final designs. Technical progress report, December 12, 1988--September 30, 1989". United States. doi:10.2172/453035. https://www.osti.gov/servlets/purl/453035.
@article{osti_453035,
title = {Nuclear Island Engineering MHTGR [Modular High-Temperature Gas-cooled Reactor] preliminary and final designs. Technical progress report, December 12, 1988--September 30, 1989},
author = {NONE},
abstractNote = {This report summarizes the Department of Energy (DOE)-funded work performed by General Atomics (GA) under the Nuclear Island Engineering (NIE)-Modular High-Temperature Gas-cooled Reactor (MHTGR) Preliminary and Final Designs Contract DE-AC03-89SF17885 for the period December 12, 1988 through September 30, 1989. This reporting period is the first (partial) fiscal year of the 5-year contract performance period. The objective of DOE`s MHTGR program is to advance the design from the conceptual design phase into preliminary design and then on to final design in support of the Nuclear Regulatory Commission`s (NRC`s) design review and approval of the MHTGR Design Team, is focused on the Nuclear Island portion of the technology and design, primarily in the areas of the reactor and internals, fuel characteristics and fuel fabrication, helium services systems, reactor protection, shutdown cooling, circulator design, and refueling system. Maintenance and implementation of the functional methodology, plant-level analysis, support for probabilistic risk assessment, quality assurance, operations, and reliability/availability assessments are included in GA`s scope of work.},
doi = {10.2172/453035},
journal = {},
number = ,
volume = ,
place = {United States},
year = 1989,
month =
}

Technical Report:

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  • 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.
  • The Reactor Cavity Cooling System (RCCS) of the Modular High- Temperature Gas-Cooled Reactor (MHTGR) proposed by the U.S. Department of Energy is designed to remove the nuclear afterheat passively in the event that neither the heat transport system nor the shutdown cooling circulator subsystem is available. A computer dynamic simulation for the physical and mathematical modeling of and RCCS is described here. Two conclusions can be made form computations performed under the assumption of a uniform reactor vessel temperature. First, the heat transferred across the annulus from the reactor vessel and then to ambient conditions is very dependent on themore » surface emissivities of the reactor vessel and RCCS panels. These emissivities should be periodically checked to ensure the safety function of the RCCS. Second, the heat transfer from the reactor vessel is reduced by a maximum of 10% by the presence of steam at 1 atm in the reactor cavity annulus for an assumed constant in the transmission of radiant energy across the annulus can be expected to result in an increase in the reactor vessel temperature for the MHTGR. Further investigation of participating radiation media, including small particles, in the reactor cavity annulus is warranted. 26 refs., 7 figs., 1 tab.« less
  • Experiments and calculations indicate that laser-induced fluorescence (LIF) lacks the sensitivity needed for sorptivity measurements of I{sub 2} or other molecular species at partial pressures below 10{sup {minus}11} atm. Although the technique may have sufficient sensitivity for measurements of atomic species, the species of interest are, in all likelihood, not atomic. Methods of measurement which would allow the determination of species are proposed. 9 refs., 6 figs.
  • 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 validate these methods is identified. The additional validation work includes comparison of calculations with available experimental data, benchmark comparison of calculations with available experimental data, benchmark comparisons with other validated codes,more » results from a cooperative program now underway at the Arbeitsgemeinschaft Versuchs-Reaktor GmbH (AVR) facility in Germany, results from a planned series of experiments on the Compact Nuclear Power Source (CNPS) facility at Los Alamos, and detailed documentation of all V&V studies. In addition, information will be obtained from planned international cooperative agreements to provide supplemental data for V&V. The regulatory technology development plan will be revised to include these additional experiments. A work schedule and cost estimate for completing this plan is also provided. This work schedule indicates the timeframe in which major milestones must be performed in order to complete V&V tasks prior to the issuance of preliminary design approval from the NRC. The cost to complete V&V tasks for core physics computational methods is estimated to be $2.2M. 41 refs., 13 figs., 8 tabs.« less
  • A team of electric utility representatives conducted an in-depth, independent evaluation of the current Modular High Temperature Gas-Cooled Reactor (MHTGR) design. The emphasis was on the fuel design with respect to safety, the licensability of the proposed containment concept, refueling operations and equipment, spent fuel storage capacity, staffing projections, and the economic competitiveness. Specific comments and recommendations are provided as a contribution towards enhancing the MHTGR design, licensability and acceptance from a utility's view. Individual sections have been indexed separately for inclusion on the data base.