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

Part of:
Proceedings of the KNS 2015 Spring Meeting

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