Published 2007 | Version v1
Book

FCI phenomena uncertainties impacting predictability of dynamic loading of reactor structures (Serena programme)

  • 1. CEA Cadarache, 13 - Saint Paul lez Durance (France)
  • 2. Korea Maritime Univ. (Korea, Republic of)
  • 3. Nuclear Regulatory Commission (United States)
  • 4. CEA Grenoble, 38 (France)
  • 5. Institute fur Kernenergetik und Energiesysteme (Germany)
  • 6. Wisconsin Univ., Madison, WI (United States)
  • 7. Forschungszentrum Karlsruhe (Germany)
  • 8. Institut de Radioprotection et Surete Nucleaire, 92 - Fontenay aux Roses (France)
  • 9. Electrogorsk Research and Engineering Centre (Russian Federation)
  • 10. Japan Atomic Energy Research Institute (Japan)
  • 11. Nuclear Power Engineering Corporation (Japan)
  • 12. Korea Atomic Energy Research Institute (Korea, Republic of)
  • 13. Korea Institute of Nuclear Safety (Korea, Republic of)
  • 14. California Univ., Santa Barbara, CA (United States)

Description

The paper presents the results of Phase 1 of OECD SERENA programme on fuel-coolant interaction under the aspect of the implications uncertainties on FCI phenomena may have on the predictability of steam explosion induced loads. SERENA, in its Phase 1, made a status of the predictive capabilities of the FCI codes through comparative calculations of most relevant existing experiments and reactor cases. All the codes were able to calculate reactors situations. The way they have been used in the exercise, the calculated in-vessel loads were found far below the capacity of a typical intact vessel and above the capacity of a typical cavity. Confidence in these conclusions are challenged by the large scatter of the results, and by the uncertainties related to the description of the flow patterns in the pre-mixing phase, in particular void fraction evolution, and to the missing physical justification of the reduced energetics observed with corium melts. Addressing these issues as well as considering other reactor situations is required to confirm these conclusions for in-vessel steam explosion and quantify the safety margins for ex-vessel steam explosion. (authors)

Part of:
Evaluation of uncertainties in relation to severe accidents and level-2 probabilistic safety analysis

Additional details

Publishing Information

Publisher
Organisation for Economic Co-Operation and Development - Nuclear Energy Agency - Committee on the Safety of Nuclear Installations
Imprint Place
Paris (France)
Imprint Title
Evaluation of uncertainties in relation to severe accidents and level-2 probabilistic safety analysis
Imprint Pagination
1002 p.
Journal Page Range
p. 494-529

Conference

Title
Workshop proceedings evaluation of uncertainties in relation to severe accidents and level-2 probabilistic safety analysis
Dates
7-9 Nov 2005
Place
Aix-en-Provence (France)

INIS

Country of Publication
France
Country of Input or Organization
Nuclear Energy Agency of the OECD (NEA)
INIS RN
39033931
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS; S42: ENGINEERING;
Resource subtype / Literary indicator
Conference
Descriptors DEI
COMPUTERIZED SIMULATION; COORDINATED RESEARCH PROGRAMS; CORIUM; DATA COVARIANCES; EXPLOSIONS; FUEL-COOLANT INTERACTIONS; MELTDOWN; REACTOR SAFETY; STEAM; TEST FACILITIES; THERMAL HYDRAULICS; VALIDATION; VOID FRACTION
Descriptors DEC
ACCIDENTS; FLUID MECHANICS; HYDRAULICS; MECHANICS; REACTOR ACCIDENTS; RESEARCH PROGRAMS; SAFETY; SIMULATION; TESTING

Optional Information

Notes
7 refs.