Published July 1995 | Version v1
Report Open

Development of the advanced PHWR technology -Design and analysis of CANDU advanced fuel-

Creators

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

Description

This is the '94 annual report of the CANDU advanced fuel design and analysis project, and describes CANFLEX fuel design and mechanical integrity analysis, reactor physics analysis and safety analysis of the CANDU-6 with the CANFLEX-NU. The following is the R and D scope of this fiscal year : (1) Detail design of CANFLEX-NU and detail analysis on the fuel integrity, reactor physics and safety. (a) Detail design and mechanical integrity analysis of the bundle (b) CANDU-6 refueling simulation, and analysis on the Xe transients and adjuster system capability (c) Licensing strategy establishment and safety analysis for the CANFLEX-NU demonstration demonstration irradiation in a commercial CANDU-6. (2) Production and revision of CANFLEX-NU fuel design documents (a) Production and approval of CANFLEX-NU reference drawing, and revisions of fuel design manual and technical specifications (b) Production of draft physics design manual. (3) Basic research on CANFLEX-SEU fuel. 55 figs, 21 tabs, 45 refs. (Author)

Availability note (English)

MF available from INIS under the Report Number.

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Additional details

Publishing Information

Imprint Pagination
227 p.
Report number
KAERI-RR--1465/94

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
27015701
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Descriptors DEI
CANDU TYPE REACTORS; COMPUTER CODES; COMPUTERIZED SIMULATION; FUEL CYCLE; FUEL ELEMENT CLUSTERS; FUEL RODS; NUCLEAR FUELS; REACTOR FUELING; SAFETY ANALYSIS
Descriptors DEC
ENERGY SOURCES; FUEL ASSEMBLIES; FUEL ELEMENTS; FUELS; HEAVY WATER MODERATED REACTORS; MATERIALS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; SIMULATION; THERMAL REACTORS