Published October 2013 | Version v1
Miscellaneous Metadata-only

Preliminary Assessment of a PWR Steam Generator Analysis Code, CUPID-SG

Creators

  • 1. Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

Description

CUPID-SG has been developed to analyze the thermo-hydraulic performance of steam generators of PWR. In this work, the CUPID-SG was verified with conceptual problems of thermal conduction and porous media approach, and validated by comparing the prediction on FRIGG, which is one of the test cases of ATHOS3 code

Part of:
Proceedings of the KNS Fall meeting

Additional details

Publishing Information

Publisher
KNS
Imprint Place
Daejeon (Korea, Republic of)
Imprint Title
Proceedings of the KNS Fall meeting
Imprint Pagination
[1 CD-ROM]
Journal Page Range
[2 p.]

Conference

Title
2013 Fall meeting of the KNS
Dates
23-25 Oct 2013
Place
Kyungju (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
45082306
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
A CODES; C CODES; PWR TYPE REACTORS; STEAM GENERATORS; THERMAL CONDUCTION; THERMAL HYDRAULICS; VALIDATION; VERIFICATION
Descriptors DEC
BOILERS; COMPUTER CODES; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; FLUID MECHANICS; HEAT TRANSFER; HYDRAULICS; MECHANICS; POWER REACTORS; REACTORS; TESTING; THERMAL REACTORS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
2 refs, 4 figs