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IPWR-900

Indian pressurized water nuclear reactor design

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General referenceInterpretive dossier study · Crown Archives visual atlas
Record originEnglish Wikipedia
Text licenseCC BY-SA 4.0
Source revisionSep 9, 2026
Entity authorityQ106464234
Source-derived summary

The Indian Pressurized Water Reactor-900 (IPWR-900) is a class of pressurized water reactors being designed by the Bhabha Atomic Research Centre (BARC) in partnership with the Nuclear Power Corporation of India Limited to supplement the Indian three-stage nuclear power programme.

History

BARC has developed an 83 MW compact light water reactor known as CLWR-B1 for the Indian Navy's Arihant-class submarine program which includes a prototype reactor operating at Kalpakkam since 2002 and was made operational in the INS Arihant in 2013. The experience gained in the naval reactor program is being used to develop a commercial electricity generation reactor of 900 MWe capacity.

To support the industrial capacity to fabricate the large forgings for a reactor pressure vessel, a heavy forge unit has been set up as a joint venture by the Nuclear Power Corporation of India Limited (NPCIL) and Indian engineering conglomerate Larsen & Toubro's subsidiary L&T Special Steels and Heavy Forgings Limited in Hazira, Gujarat. The joint venture has set up a 9000-ton forging press and plans to increase it to 17,000 tons. BARC reported the completion of manufacture of test forgings in August 2021 and confirmed the technological know-how and capability to manufacture forgings of thicknesses 350 mm to 750 mm essential to manufacturing of reactor pressure vessels for pressurized water reactor program.

Indian nuclear activities regulator Atomic Energy Regulatory Board carried out the Pre-Consenting design review for the design in the fiscal year 2015–16.

India is planning to reduce import dependence and to enter the export chain through this effort.

Design

The IPWR design is planned to retain commonality of majority of non-nuclear island components of the design with the IPHWR-700 pressurized heavy-water reactors currently in use to limit design timelines and construction costs. The steam generator design and configuration will also be adopted from the IPHWR-700 design.

Editorial summary

“IPWR-900” enters the record as indian pressurized water nuclear reactor design. Crown Archives preserves that source wording while asking what IPWR-900, Indian and pressurized can confirm, complicate or overturn.

Editorial reviewA dependable orientation record for establishing vocabulary, names and a first evidence trail. The current lead gives the account dated anchors—2002, 2013, 2021, 2015—that can be checked directly. The selected authority fields contribute no independent date. Its strongest next move is a source search built around IPWR-900, Indian and pressurized.
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The citation trail is more important than the brevity of the summary: it shows where individual claims can be examined in context. The source revision retrieved here is dated Sep 9, 2026. The linked authority identifier is Q106464234. None of the 0 selected statements returned an explicit reference. The first chronological checks are 2002, 2013, 2021 and 2015.

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This entry incorporates text from IPWR-900” on English Wikipedia. Contributors are listed in the page history. Text is available under the Creative Commons Attribution-ShareAlike 4.0 License. Selected authority identifiers and statements are retrieved from Wikidata under CC0; their references and qualifiers remain part of the verification path.