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A study on KMRR utilization for fuel development

Technical Report:

Abstract

The most effective utilization scheme of the KMRR was studied in the field of nuclear fuel development through reviewing literatural documents on irradiation facilities and in-pile test. It is suggested that the KMRR should be used for verification tests of advanced fuels and for power ramping / cycling tests of fuel rods. In addition, the characterization tests for fuel development and the basic material research should be also performed. In-pile loops for fuel verification and/or power ramping / cycling tests are proposed to be installed in advance, and capsules are necessary for power ramping / cycling tests, fuel characterization tests and / or material tests. Instrumentation technologies for thermocouple, SPND (Self-Powered Neutron Detector) and pressure transducer, and the in-situ dimensional measuring systems have to be developed to obtain the useful and various results from irradiation tests in the KMRR. A mock-up test rod for characterizing fuel thermal response was manufactured and the related technologies as well as the design specification were set up. An equipment for microdrilling and grooving of fuel pellets and an apparatus for diffusion-bonding between zircaloy-4 and stainless steel were made. A study to verify the integrity of test rod weldments is presented using out-of pile corrosion  More>>
Authors:
Kang, Young Hwan; Ryu, Woo Seog; Park, Ji Yeon; Joo, Kee Nam; Park, Jong Man; Park, Se Jin [1] 
  1. Korea Atomic Energy Research Inst., Daeduk (Korea, Republic of)
Publication Date:
Jan 01, 1991
Product Type:
Technical Report
Report Number:
KAERI/RR-964/90
Reference Number:
SCA: 220600; 220300; PA: AIX-23:015081; SN: 92000646950
Resource Relation:
Other Information: PBD: Jan 1991
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; FUEL RODS; IRRADIATION; RESEARCH REACTORS; ALLOY-ZR98SN-4; CORROSION; FABRICATION; FUEL ELEMENT CLUSTERS; STAINLESS STEELS; TEMPERATURE MEASUREMENT; THERMOCOUPLES; WELDED JOINTS; 220600; 220300; RESEARCH, TEST, TRAINING, PRODUCTION, IRRADIATION, MATERIALS TESTING REACTORS; FUEL ELEMENTS
OSTI ID:
10113687
Research Organizations:
Korea Atomic Energy Research Inst., Daeduk (Korea, Republic of)
Country of Origin:
Korea, Republic of
Language:
Korean
Other Identifying Numbers:
Other: ON: DE92615116; TRN: KR9100118015081
Availability:
OSTI; NTIS (US Sales Only); INIS
Submitting Site:
INIS
Size:
164 p.
Announcement Date:
Jun 30, 2005

Technical Report:

Citation Formats

Kang, Young Hwan, Ryu, Woo Seog, Park, Ji Yeon, Joo, Kee Nam, Park, Jong Man, and Park, Se Jin. A study on KMRR utilization for fuel development. Korea, Republic of: N. p., 1991. Web.
Kang, Young Hwan, Ryu, Woo Seog, Park, Ji Yeon, Joo, Kee Nam, Park, Jong Man, & Park, Se Jin. A study on KMRR utilization for fuel development. Korea, Republic of.
Kang, Young Hwan, Ryu, Woo Seog, Park, Ji Yeon, Joo, Kee Nam, Park, Jong Man, and Park, Se Jin. 1991. "A study on KMRR utilization for fuel development." Korea, Republic of.
@misc{etde_10113687,
title = {A study on KMRR utilization for fuel development}
author = {Kang, Young Hwan, Ryu, Woo Seog, Park, Ji Yeon, Joo, Kee Nam, Park, Jong Man, and Park, Se Jin}
abstractNote = {The most effective utilization scheme of the KMRR was studied in the field of nuclear fuel development through reviewing literatural documents on irradiation facilities and in-pile test. It is suggested that the KMRR should be used for verification tests of advanced fuels and for power ramping / cycling tests of fuel rods. In addition, the characterization tests for fuel development and the basic material research should be also performed. In-pile loops for fuel verification and/or power ramping / cycling tests are proposed to be installed in advance, and capsules are necessary for power ramping / cycling tests, fuel characterization tests and / or material tests. Instrumentation technologies for thermocouple, SPND (Self-Powered Neutron Detector) and pressure transducer, and the in-situ dimensional measuring systems have to be developed to obtain the useful and various results from irradiation tests in the KMRR. A mock-up test rod for characterizing fuel thermal response was manufactured and the related technologies as well as the design specification were set up. An equipment for microdrilling and grooving of fuel pellets and an apparatus for diffusion-bonding between zircaloy-4 and stainless steel were made. A study to verify the integrity of test rod weldments is presented using out-of pile corrosion test. (Author).}
place = {Korea, Republic of}
year = {1991}
month = {Jan}
}