Modular High Temperature Gas-cooled Reactor Plant Design Duty Cycle. Revision 3

Modular High Temperature Gas-cooled Reactor Plant Design Duty Cycle. Revision 3
Author:
Publisher:
Total Pages: 81
Release: 1989
Genre:
ISBN:

This document defines the Plant Design Duty Cycle (PCDC) for the Modular High Temperature Gas-cooled Reactor (MHTGR). The duty cycle is a set of events and their design number of occurrences over the life of the plant for which the MHTGR plant shall be designed to ensure that the plant meets all the top-level requirements. The duty cycle is representative of the types of events to be expected in multiple reactor module-turbine plant configurations of the MHTGR. A synopsis of each PDDC event is presented to provide an overview of the plant response and consequence. 8 refs., 1 fig., 4 tabs.

Overall Plant Design Specification Modular High Temperature Gas-cooled Reactor. Revision 9

Overall Plant Design Specification Modular High Temperature Gas-cooled Reactor. Revision 9
Author:
Publisher:
Total Pages: 41
Release: 1990
Genre:
ISBN:

Revision 9 of the ''Overall Plant Design Specification Modular High Temperature Gas-Cooled Reactor, '' DOE-HTGR-86004 (OPDS) has been completed and is hereby distributed for use by the HTGR Program team members. This document, Revision 9 of the ''Overall Plant Design Specification'' (OPDS) reflects those changes in the MHTGR design requirements and configuration resulting form approved Design Change Proposals DCP BNI-003 and DCP BNI-004, involving the Nuclear Island Cooling and Spent Fuel Cooling Systems respectively.

Advances in High Temperature Gas Cooled Reactor Fuel Technology

Advances in High Temperature Gas Cooled Reactor Fuel Technology
Author: International Atomic Energy Agency
Publisher:
Total Pages: 639
Release: 2012-06
Genre: Business & Economics
ISBN: 9789201253101

This publication reports on the results of a coordinated research project on advances in high temperature gas cooled reactor (HTGR) fuel technology and describes the findings of research activities on coated particle developments. These comprise two specific benchmark exercises with the application of HTGR fuel performance and fission product release codes, which helped compare the quality and validity of the computer models against experimental data. The project participants also examined techniques for fuel characterization and advanced quality assessment/quality control. The key exercise included a round-robin experimental study on the measurements of fuel kernel and particle coating properties of recent Korean, South African and US coated particle productions applying the respective qualification measures of each participating Member State. The summary report documents the results and conclusions achieved by the project and underlines the added value to contemporary knowledge on HTGR fuel.

Design Data Needs Modular High-temperature Gas-cooled Reactor. Revision 2

Design Data Needs Modular High-temperature Gas-cooled Reactor. Revision 2
Author:
Publisher:
Total Pages: 393
Release: 1987
Genre:
ISBN:

The Design Data Needs (DDNs) provide summary statements for program management, of the designer's need for experimental data to confirm or validate assumptions made in the design. These assumptions were developed using the Integrated Approach and are tabulated in the Functional Analysis Report. These assumptions were also necessary in the analyses or trade studies (A/TS) to develop selections of hardware design or design requirements. Each DDN includes statements providing traceability to the function and the associated assumption that requires the need.

Balance of Plant Analysis for High Temperature Gas Cooled Reactors

Balance of Plant Analysis for High Temperature Gas Cooled Reactors
Author: Chunyun Wang
Publisher: LAP Lambert Academic Publishing
Total Pages: 220
Release: 2009-09
Genre:
ISBN: 9783838313894

As a Generation IV nuclear system, the High Temperature Gas Cooled Reactor (HTGR) desires a gas turbine cycle (Brayton cycle) as the power conversion system for it to achieve economic competitiveness. The availability of compact heat exchangers and helium turbo-machinery are thus the critical enabling technology for the gas turbine cycle. This book performs an extensive study on the power conversion system: design constraints, cycle variations, compact heat exchangers, high efficiency helium turbo-machinery and cycle control methods. A detailed steady state and dynamic model is developed for studying the cycle design in terms of efficiency and controllability. An indirect closed helium cycle design is developed in this book by identifying key advances in the technology that could reasonably be expected to be achieved with limited R&D. The modular conceptual design for the intermediate heat exchanger (IHX) and recuperator is also performed.

MHTGR [modular High-temperature Gas-cooled Reactor] Core Physics Validation Plan

MHTGR [modular High-temperature Gas-cooled Reactor] Core Physics Validation Plan
Author:
Publisher:
Total Pages:
Release: 1988
Genre:
ISBN:

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, 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.

MHTGR (Modular High-Temperature Gas-Cooled Reactor) Design and Development Status

MHTGR (Modular High-Temperature Gas-Cooled Reactor) Design and Development Status
Author:
Publisher:
Total Pages:
Release: 1988
Genre:
ISBN:

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 materials. The design utilizes passively safe features which provide a higher margin of safety and investment protection than current generation reactors. The design has been evaluated to be economically attractive relative to modern coal fired plants. The design and development program is a cooperative effort by the US government, the utilities and the nuclear industry. 8 refs., 4 figs., 4 tabs.

Safety and Licensing of MHTGR (Modular High Temperature Gas Cooled Reactor).

Safety and Licensing of MHTGR (Modular High Temperature Gas Cooled Reactor).
Author:
Publisher:
Total Pages:
Release: 1987
Genre:
ISBN:

The Modular High Temperature Gas Cooled Reactor (MHTGR) design meets stringent top-level regulatory and user safety requirements that require that the normal and off-normal operation of the plant not disturb the public's day-to-day activities. Quantitative, top-level regulatory criteria have been specified from US NRC and EPA sources to guide the design. The user/utility group has further specified that these criteria be met at the plant boundary. The focus of the safety approach has then been centered on retaining the radionuclide inventory within the fuel by removing core heat, controlling chemical attack, and by controlling heat generation. The MHTGR is shown to passively meet the stringent requirements with margin. No operator action is required and the plant is insensitive to operator error.