NDLI: CAREM-25: Energy and Safety for the Future

Content Provider	The American Society of Mechanical Engineers (ASME) Digital Collection
Author	Ba´ez, La´zaro E. Pomier
Copyright Year	2002
Abstract	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.
Sponsorship	Power Division
Starting Page	1047
Ending Page	1054
Page Count	8
File Format	PDF
ISBN	0791836177
DOI	10.1115/IJPGC2002-26187
e-ISBN	0791836010
Conference Proceedings	2002 International Joint Power Generation Conference
Language	English
Publisher Date	2002-06-24
Publisher Place	Scottsdale, Arizona, USA
Access Restriction	Subscribed
Subject Keyword	Water Reactor vessels Vessels Containers Boilers Natural convection Fuels Design Electric power generation Personnel management Coolants Safety Nuclear reactors Nuclear power stations Pressurized water reactors Failure
Content Type	Text
Resource Type	Article

Sl.	Authority	Responsibilities	Communication Details
1	Ministry of Education (GoI), Department of Higher Education	Sanctioning Authority	https://www.education.gov.in/ict-initiatives
2	Indian Institute of Technology Kharagpur	Host Institute of the Project: The host institute of the project is responsible for providing infrastructure support and hosting the project	https://www.iitkgp.ac.in
3	National Digital Library of India Office, Indian Institute of Technology Kharagpur	The administrative and infrastructural headquarters of the project	Dr. B. Sutradhar bsutra@ndl.gov.in
4	Project PI / Joint PI	Principal Investigator and Joint Principal Investigators of the project	Dr. B. Sutradhar bsutra@ndl.gov.in Prof. Saswat Chakrabarti will be added soon
5	Website/Portal (Helpdesk)	Queries regarding NDLI and its services	support@ndl.gov.in
6	Contents and Copyright Issues	Queries related to content curation and copyright issues	content@ndl.gov.in
7	National Digital Library of India Club (NDLI Club)	Queries related to NDLI Club formation, support, user awareness program, seminar/symposium, collaboration, social media, promotion, and outreach	clubsupport@ndl.gov.in
8	Digital Preservation Centre (DPC)	Assistance with digitizing and archiving copyright-free printed books	dpc@ndl.gov.in
9	IDR Setup or Support	Queries related to establishment and support of Institutional Digital Repository (IDR) and IDR workshops	idr@ndl.gov.in

Severe Accident Improvements for CAREM-25 to Arrest Reactor Vessel Meltdown Sequences

Design Characteristics of Ulchin Nuclear Power Units 5&6

Approach to UK SMR Component Design

Heavy Components Replacement in Nuclear Power Plants: Guidelines and Experiences

French PWR Nuclear Power Plants Steam Generators and Reactor Pressure Vessel Heads Aging Management Criteria and Replacement Strategy

Aging Management of Reactor Coolant System Mechanical Components in Pressurized Water Reactors for License Renewal

ASME Subcommittee XI Initiatives for the Detection and Correction of Boric Acid Corrosion of Pressure Retaining Low Alloy Steel Components in Pressurized Water Reactor Plants

Design Issues and Considerations During Reactor Vessel Head Replacement, Steam Generator Replacement, and Steam Generator Snubber Elimination at Nuclear Power Plants

Application of Joint Boring Technique in Solving RCL Wall Thickness Problem

CAREM-25: Energy and Safety for the Future

Similar Documents

Severe Accident Improvements for CAREM-25 to Arrest Reactor Vessel Meltdown Sequences

Design Characteristics of Ulchin Nuclear Power Units 5&6

Approach to UK SMR Component Design

Heavy Components Replacement in Nuclear Power Plants: Guidelines and Experiences

French PWR Nuclear Power Plants Steam Generators and Reactor Pressure Vessel Heads Aging Management Criteria and Replacement Strategy

Aging Management of Reactor Coolant System Mechanical Components in Pressurized Water Reactors for License Renewal

ASME Subcommittee XI Initiatives for the Detection and Correction of Boric Acid Corrosion of Pressure Retaining Low Alloy Steel Components in Pressurized Water Reactor Plants

Design Issues and Considerations During Reactor Vessel Head Replacement, Steam Generator Replacement, and Steam Generator Snubber Elimination at Nuclear Power Plants

Application of Joint Boring Technique in Solving RCL Wall Thickness Problem

CAREM-25: Energy and Safety for the Future