Published 2022 | Version v1
Report Metadata-only

Considerations on the new safety paradigm provided by liquid-fuelled reactors - Illustration on the MSFR concept

Creators

  • 1. Grenoble INP (France)
  • 2. Universite Grenoble Alpes (France)
  • 3. LPSC-IN2P3-CNRS (France)
  • 4. IRESNE (France)
  • 5. DES (France)
  • 6. CEA Cadarache (France)
  • 7. Framatome Lyon (France)
  • 8. Framatome Paris La Défense (France)
  • 9. IMT-Atlantique (France)
  • 10. CNRS/IN2P3 (France)
  • 11. SUBATECH (France)

Description

Liquid-fuelled molten salt reactors (MSRs) may be different in terms of design, operation and safety issues compared to large water-cooled nuclear power plants (NPPs). This paper presents in a first part an analysis of the safety paradigm for such systems, based on the identification of safety-related innovations of such MSRs. The second part of the article is dedicated to an application to the Molten Salt Fast Reactor (MSFR) concept developed in France by CNRS to illustrate the safety principles application on a specific design representative of similar liquid-fuelled MSRs.

Part of:
Technical Meeting on the Safety of High Temperature Gas Cooled Reactors and Molten Salt Reactors. Book of Abstracts

Additional details

Identifiers

URL
https://conferences.iaea.org/event/294/;

Publishing Information

Imprint Title
Technical Meeting on the Safety of High Temperature Gas Cooled Reactors and Molten Salt Reactors. Book of Abstracts
Imprint Pagination
24 p.
Journal Page Range
p. 9-10
Report number
INIS-XA--22M2995

Conference

Title
Technical Meeting on the Safety of High Temperature Gas Cooled Reactors and Molten Salt Reactors
Dates
9-13 May 2022
Place
Vienna (Austria)

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
54005069
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
FAST REACTORS; LIQUID FUELS; MOLTEN SALT REACTORS; MOLTEN SALTS; NUCLEAR POWER PLANTS; REACTOR DESIGN; REACTOR OPERATION; REACTOR SAFETY; WATER COOLED REACTORS
Descriptors DEC
DESIGN; EPITHERMAL REACTORS; FUELS; NUCLEAR FACILITIES; OPERATION; POWER PLANTS; REACTOR LIFE CYCLE; REACTORS; SAFETY; SALTS; THERMAL POWER PLANTS

Optional Information

Notes
5 refs.