Published April 2015 | Version v1
Book

Evaluation method of the verification test items for the transient analysis code of sodium cooled fast reactor

  • 1. FNC Technology Co., Seoul National University 135-308, Kwanak-ro 1, Kwanak-gu, Seoul, 151-742 (Korea, Republic of)
  • 2. Korea Institute of Nuclear Safety, Gwahak-ro, Yuseong-gu, Daejeon, 305-338 (Korea, Republic of)

Description

GEN-IV reactors as a kind of advanced reactors including SFRs (Sodium Fast Rectors) are now world-widely under development with the aims of highly economical advances and safety enhancement. Together with the development of the advanced reactors, transient and accident analysis method for water reactors has also progressed. However, since the advanced reactors are fundamentally different from the water reactors, regulatory tools (code, data, etc.) may not be further directly applicable to the advanced reactor designs. For the reliable regulatory decision in accident analysis the analysis code should be sufficiently verified and validated. Several code and standards have been applied to light water reactors, for example Reg. Guide 1.157, Reg. Guide 1.203, NUREG-1230, ASME V&V 10.1-2012, and so on. Recently CFD (Computational Fluid Dynamics) has been gradually adopted in nuclear safety analysis and guidelines on the usage have also been suggested such as ECORA (Evaluation of Computational fluid dynamic methods for reactor safety analysis). The critical review of such materials gives insights for the evaluation method for the transient analysis code and this will be discussed in this paper. The key words in these materials are PIRT (Phenomena Identification and Ranking Table) and uncertainty analysis including bias. Another one important feature is that the regulatory bodies do not have the same degree of data as are available for light water reactors. Some proposed an international cooperative research and exploration as only a practical way. KINS (Korea Institute of Nuclear Safety) has devoted much effort in such a problem because Korean nuclear industry are now under pursuance of construction of SFR. As a first research step for the licensing process in SFR accident analysis a phenomena identification table was developed from the intensive research and independent reviews. Ranking process was not performed yet but screening process was conducted. So each item in the table is believed to be worthy while to consider. Such items will be discussed together with the evaluation method of the verification test items for the transient analysis code. (author)

Part of:
Fast Reactors and Related Fuel Cycles: Safe Technologies and Sustainable Scenarios (FR13). COMPANION CD-ROM. Proceedings of an International Conference

Additional details

Identifiers

Publishing Information

Publisher
IAEA
Imprint Place
Vienna (International Atomic Energy Agency (IAEA))
ISBN
978-92-0-104114-2
Imprint Title
Fast Reactors and Related Fuel Cycles: Safe Technologies and Sustainable Scenarios (FR13). COMPANION CD-ROM. Proceedings of an International Conference
Imprint Pagination
[1 CD-ROM]
Series
Proceedings Series
Journal Page Range
10 p.
ISSN
0074-1884

Conference

Title
International Conference on Fast Reactors and Related Fuel Cycles: Safe Technologies and Sustainable Scenarios
Acronym
FR13
Dates
4-7 Mar 2013
Place
Paris (France)

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
46091114
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
COMPUTERIZED SIMULATION; FLUID MECHANICS; REACTOR ACCIDENTS; SAFETY ANALYSIS; SODIUM COOLED REACTORS; TRANSIENTS; VERIFICATION; WATER COOLED REACTORS; WATER MODERATED REACTORS
Descriptors DEC
ACCIDENTS; LIQUID METAL COOLED REACTORS; MECHANICS; REACTORS; SIMULATION

Optional Information

Notes
20 refs., 6 figs., 1 tab.
Secondary number(s)
IAEA-CN--199/470