Study of cooling strategy for pressure vessel in pool research reactor at accident situation

Kerntechnik ◽  
2020 ◽  
Vol 85 (2) ◽  
pp. 88-97
Author(s):  
D. Zhang ◽  
X. Ran ◽  
Y. Zhang ◽  
H. Zhang
Keyword(s):  
Pressure Vessel ◽  
Research Reactor ◽  
Cooling Strategy

Study of cooling strategy for pressure vessel in pool research reactor at accident situation

Kerntechnik ◽  
2020 ◽  
Vol 85 (2) ◽  
pp. 88-97
Author(s):  
D. Zhang ◽  
X. Ran ◽  
Y. Zhang ◽  
H. Zhang
Keyword(s):  
High Power ◽  
Pressure Vessel ◽  
Research Reactor ◽  
Heat Removal ◽  
Cooling Strategy ◽  
Residual Heat

Abstract Pressure vessel in pool layout is usually used in high power and middle pressure research reactor, Flow inversion and residual heat removal is important problem. The heat removal strategy at accident situation for a pressure vessel in pool layout research reactor was studied in the paper, many cases was researched for the ability of heat removal and safety of core.

scholarly journals Fatigue Design Curves for 6061-T6 Aluminum

1997 ◽  
Vol 119 (2) ◽  
pp. 211-215 ◽  
Author(s):  
G. T. Yahr
Keyword(s):  
Base Metal ◽  
Neutron Source ◽  
Pressure Vessel ◽  
Research Reactor ◽  
Mean Stress ◽  
Design Curve ◽  
Stress Effects ◽  
Fatigue Design ◽  
Fatigue Data ◽  
Class 1

A request has been made to the ASME Boiler and Pressure Vessel Committee that 6061-T6 aluminum be approved for use in the construction of Class 1 welded nuclear vessels so it can be used for the pressure vessel of the Advanced Neutron Source research reactor. Fatigue design curves with and without mean stress effects have been proposed. A knock-down factor of 2 is applied to the design curve for evaluation of welds. The basis of the curves is explained. The fatigue design curves are compared to fatigue data from base metal and weldments.

The Bandsaw: A Highly Sophisticated Dismantling Technique for the Karlsruhe Multi Purpose Research Reactor

2003 ◽  
Author(s):  
U. Leffrang ◽  
D. Stanke ◽  
E. Prechtl ◽  
W. Suessdorf
Keyword(s):  
Pressure Vessel ◽  
Research Reactor ◽  
Reactor Pressure Vessel ◽  
Reactor Pressure

For the dry dismantling and segmentation of dedicated components within the reactor pressure vessel (RPV) of the Karlsruhe Multi Purpose Research Reactor (MZFR) a bandsaw has been applied. The general decommissioning concept for the MZFR as well as constructional details of the bandsaw itself and the experience gained so far during the segmentation of the RPV closure head and the upper spacer are given with the present paper.

CAREM-25: Energy and Safety for the Future

2002 ◽  
Author(s):  
La´zaro E. Pomier Ba´ez
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Pressure Vessel ◽  
Nuclear Power ◽  
Research Reactor ◽  
Reactor Pressure Vessel ◽  
Water Desalination ◽  
Pressurized Water ◽  
Management Actions ◽  
Reactor Pressure

The CAREM-25 is an advanced small nuclear power plant being jointly developed by CNEA (Comisio´n Nacional de Energi´a Ato´mica) and INVAP S. E. in Argentina. CAREM is a modular 100 MWt pressurized water reactor with integral steam generators designed to be used for electricity generation (25 MWe) or as a research reactor or for water desalination. The plant has its entire primary coolant system within the reactor pressure vessel (hence ‘integral’ PWR), self-pressurized and relying entirely on natural convection. Fuel is standard 3.4% enriched PWR fuel, with burnable poison, and is refueled annually. It is a mature design, which could be deployed within a decade. The CAREM reactor shows itself as a design capable to fill the existing gap between a research reactor and a full-scale commercial nuclear power plant. From this point of view, CAREM is a very attractive option for countries who have not yet developed technical capabilities, human resources, and an industrial infrastructure needed for a medium or large size nuclear units. Advanced nuclear reactor designs, such as the CAREM reactor, include several improvements related to safety issues either enhancing the passive safety functions or allowing plant operators more time to undertake different management actions against radioactive releases to the environment The enhancement and development of safety measures for this type of system are a top priority of designers. In the development of the nuclear power plant CAREM, the possibility of including a passive metallic in-vessel container in its design is being considered, to arrest the reactor pressure vessel meltdown sequence during a core damaging event, and thereof prevent its failure. The present paper will provide an overview of the CAREM-25 technology as a general purpose generation unit, and highlight the work on safety measure’s enhancements, including design modifications aiming to improve overall safety targets of the plant.

Mcc Corrosion Tests at Reference Testing Conditions for A27 Cast steel in Hanford Ground Water

1986 ◽  
Vol 84 ◽  
Author(s):  
M.D. Merz ◽  
F. Gerber ◽  
R. Wang
Keyword(s):  
Pacific Northwest ◽  
Pressure Vessel ◽  
Static Pressure ◽  
Cast Steel ◽  
Statistical Treatment ◽  
Testing Conditions ◽  
Corrosion Tests ◽  
Corrosion Rates ◽  
High Level Nuclear Waste ◽  
High Level

AbstractThe Materials Characterization Center (MCC) at Pacific Northwest Lab- oratory is performing three kinds of corrosion tests for the Basalt Waste Isolation Project (BWIP) to establish the interlaboratory reproducibility and uncertainty of corrosion rates of container materials for high-level nuclear waste. The three types of corrosion tests were selected to address two distinct conditions that are expected in a repository constructed in basalt. An air/steam test is designed to address corrosion during the operational period and static pressure vessel and flowby tests are designed to address corrosion under conditions that bound the condi ring the post-closure period of the repository.The results of tests at reference testing conditions, which were defined to facilitate interlaboratory comparison of data, are presented. Data are reported for the BWIP/MCC-105.5 Air/Steam Test, BWIP/MCC-105.1 Static Pressure Vessel, and BWIP/MC-105.4 Flowby Test. In those cases where data are available from a second laboratory, a statistical analysis of interlaboratory results is reported and expected confidence intervals for mean corrosion rates are given. Other statistical treatment of data include analyses of the effects of vessel-to-vessel variations, test capsule variations for the flowby test, and oven-to-oven variations for air/steam tests.

Stress Analyzes of a Didactic-Purpose Pressure Vessel

2019 ◽  
Author(s):  
SOFIA GLYNIADAKIS ◽  
José Tomazini ◽  
Marcelo Sampaio Martins
Keyword(s):  
Pressure Vessel
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