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Input modelling of ASSERT-PV V2R8M1 for RUFIC fuel bundle

Abstract

This report describes the input modelling for subchannel analysis of CANFLEX-RU (RUFIC) fuel bundle which has been developed for an advanced fuel bundle of CANDU-6 reactor, using ASSERT-PV V2R8M1 code. Execution file of ASSERT-PV V2R8M1 code was recently transferred from AECL under JRDC agreement between KAERI and AECL. SSERT-PV V2R8M1 which is quite different from COBRA-IV-i code has been developed for thermalhydraulic analysis of CANDU-6 fuel channel by subchannel analysis method and updated so that 43-element CANDU fuel geometry can be applied. Hence, ASSERT code can be applied to the subchannel analysis of RUFIC fuel bundle. The present report was prepared for ASSERT input modelling of RUFIC fuel bundle. Since the ASSERT results highly depend on user's input modelling, the calculation results may be quite different among the user's input models. The objective of the present report is the preparation of detail description of the background information for input data and gives credibility of the calculation results.
Publication Date:
Feb 01, 2001
Product Type:
Technical Report
Report Number:
KAERI/TR-1756/2001
Resource Relation:
Other Information: 8 refs., 5 tabs., 19 figs; PBD: Feb 2001
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; A CODES; COMPUTER CALCULATIONS; DATA ANALYSIS; ENTHALPY; FLOW RATE; FUEL CHANNELS; FUEL ELEMENT CLUSTERS; FUEL ELEMENTS; LIQUIDS; SIMULATION; THERMODYNAMICS; VAPORS; VELOCITY; VOID FRACTION
OSTI ID:
20209459
Research Organizations:
Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)
Country of Origin:
Korea, Republic of
Language:
Korean
Other Identifying Numbers:
TRN: KR0101279062426
Availability:
Available from INIS in electronic form
Submitting Site:
KRN
Size:
65 pages
Announcement Date:

Citation Formats

Park, Joo Hwan, and Suk, Ho Chun. Input modelling of ASSERT-PV V2R8M1 for RUFIC fuel bundle. Korea, Republic of: N. p., 2001. Web.
Park, Joo Hwan, & Suk, Ho Chun. Input modelling of ASSERT-PV V2R8M1 for RUFIC fuel bundle. Korea, Republic of.
Park, Joo Hwan, and Suk, Ho Chun. 2001. "Input modelling of ASSERT-PV V2R8M1 for RUFIC fuel bundle." Korea, Republic of.
@misc{etde_20209459,
title = {Input modelling of ASSERT-PV V2R8M1 for RUFIC fuel bundle}
author = {Park, Joo Hwan, and Suk, Ho Chun}
abstractNote = {This report describes the input modelling for subchannel analysis of CANFLEX-RU (RUFIC) fuel bundle which has been developed for an advanced fuel bundle of CANDU-6 reactor, using ASSERT-PV V2R8M1 code. Execution file of ASSERT-PV V2R8M1 code was recently transferred from AECL under JRDC agreement between KAERI and AECL. SSERT-PV V2R8M1 which is quite different from COBRA-IV-i code has been developed for thermalhydraulic analysis of CANDU-6 fuel channel by subchannel analysis method and updated so that 43-element CANDU fuel geometry can be applied. Hence, ASSERT code can be applied to the subchannel analysis of RUFIC fuel bundle. The present report was prepared for ASSERT input modelling of RUFIC fuel bundle. Since the ASSERT results highly depend on user's input modelling, the calculation results may be quite different among the user's input models. The objective of the present report is the preparation of detail description of the background information for input data and gives credibility of the calculation results.}
place = {Korea, Republic of}
year = {2001}
month = {Feb}
}