Published May 2015
| Version v1
Miscellaneous
Preliminary Stress Analysis for Receptacle of Prototype Sodium-cooled fast Reactor
- 1. Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)
Description
The receptacle is responsible for supporting the weight of the fuel assembly and retaining the primary sodium flow path up to the fuel assembly. In terms of preventing the core meltdown, it is important to make the receptacle design have enough structural integrity. The purpose of this paper is to evaluate the integrity of the receptacle regarding the weight loads of the dead weight and the fuel assembly following ASME code. This paper evaluated the integrity of the receptacle with respect to the design condition and the steady-state condition of the level A condition. According evaluation results, the receptacle design has enough design margins and satisfies the design criteria defined ASME code
Additional details
Publishing Information
- Publisher
- KNS
- Imprint Place
- Daejeon (Korea, Republic of)
- Imprint Title
- Proceedings of the KNS 2015 spring meeting
- Imprint Pagination
- [1 CD-ROM]
- Journal Page Range
- [3 p.]
Conference
- Title
- 2015 spring meeting of the KNS
- Dates
- 6-8 May 2015
- Place
- Jeju (Korea, Republic of)
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 47023000
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- A CODES; DESIGN; EVALUATION; FUEL ASSEMBLIES; MELTDOWN; SODIUM COOLED REACTORS; STRESS ANALYSIS
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; LIQUID METAL COOLED REACTORS; REACTOR ACCIDENTS; REACTORS
Optional Information
- Notes
- 4 refs, 5 figs, 3 tabs