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Technology development for nuclear material accountability

Technical Report:

Abstract

Using Segmented Gamma Scanning(SGS) System and coaxical Ge detector, the amounts of uranium in 55 gallon waste drums mixed with low density matrix material were determined by segmented gamma-scanning method. Various factors that influence sample measurement were identified as attenuation effects against sample container and matrix material counting loss effect by dead time and signal pile-up and radial and axial non-uniformity effects of sample. External transmission source, Yb-169, was used to correct gamma-ray attenuation by matrix material. The measure deviation caused by non-uniform distribution in the drum was minimized by rotating and dividing the drum. To calibrate the measurement system, calibration sources were prepared in the range of 50g, 100g, 300g, and 500g of U0{sub 2} powder which let it stick to thin gummed papers and mix with other matrix materials such as papers, vinyl sheets, pieces of rubber gloves in 4 each drum. Under the calibrated assay system the uncertainty of measured amounts of UO{sub 2} powder approached about 10% of absolute value at 1{sigma} and a normal flow of waste stream can be maintained at least one drum per hour. On the other hand, in an effort to ease the nuclear material accounting for and control the flow  More>>
Authors:
Hong, Jong Sook; Lee, Byung Doo; Cha, Hong Ryul; Choi, Hyoung Nai; Park, Ho Joon [1] 
  1. Korea Atomic Energy Research Inst., Daeduk (Korea, Republic of)
Publication Date:
Mar 01, 1991
Product Type:
Technical Report
Report Number:
KAERI/RR-979/90
Reference Number:
SCA: 055001; 400101; PA: AIX-23:017588; SN: 92000661379
Resource Relation:
Other Information: PBD: Mar 1991
Subject:
98 NUCLEAR DISARMAMENT, SAFEGUARDS, AND PHYSICAL PROTECTION; 37 INORGANIC, ORGANIC, PHYSICAL AND ANALYTICAL CHEMISTRY; RADIOACTIVE MATERIALS; ACCOUNTING; MATERIAL BALANCE; MATERIAL BALANCE AREA; MEASURING METHODS; NONDESTRUCTIVE ANALYSIS; SAFEGUARDS; SOLID WASTES; URANIUM DIOXIDE; 055001; 400101; TECHNICAL ASPECTS; ACTIVATION, NUCLEAR REACTION, RADIOMETRIC, AND RADIOCHEMICAL PROCEDURES
OSTI ID:
10118348
Research Organizations:
Korea Atomic Energy Research Inst., Daeduk (Korea, Republic of)
Country of Origin:
Korea, Republic of
Language:
Korean
Other Identifying Numbers:
Other: ON: DE92616880; TRN: KR9100129017588
Availability:
OSTI; NTIS (US Sales Only); INIS
Submitting Site:
INIS
Size:
152 p.
Announcement Date:
Jun 30, 2005

Technical Report:

Citation Formats

Hong, Jong Sook, Lee, Byung Doo, Cha, Hong Ryul, Choi, Hyoung Nai, and Park, Ho Joon. Technology development for nuclear material accountability. Korea, Republic of: N. p., 1991. Web.
Hong, Jong Sook, Lee, Byung Doo, Cha, Hong Ryul, Choi, Hyoung Nai, & Park, Ho Joon. Technology development for nuclear material accountability. Korea, Republic of.
Hong, Jong Sook, Lee, Byung Doo, Cha, Hong Ryul, Choi, Hyoung Nai, and Park, Ho Joon. 1991. "Technology development for nuclear material accountability." Korea, Republic of.
@misc{etde_10118348,
title = {Technology development for nuclear material accountability}
author = {Hong, Jong Sook, Lee, Byung Doo, Cha, Hong Ryul, Choi, Hyoung Nai, and Park, Ho Joon}
abstractNote = {Using Segmented Gamma Scanning(SGS) System and coaxical Ge detector, the amounts of uranium in 55 gallon waste drums mixed with low density matrix material were determined by segmented gamma-scanning method. Various factors that influence sample measurement were identified as attenuation effects against sample container and matrix material counting loss effect by dead time and signal pile-up and radial and axial non-uniformity effects of sample. External transmission source, Yb-169, was used to correct gamma-ray attenuation by matrix material. The measure deviation caused by non-uniform distribution in the drum was minimized by rotating and dividing the drum. To calibrate the measurement system, calibration sources were prepared in the range of 50g, 100g, 300g, and 500g of U0{sub 2} powder which let it stick to thin gummed papers and mix with other matrix materials such as papers, vinyl sheets, pieces of rubber gloves in 4 each drum. Under the calibrated assay system the uncertainty of measured amounts of UO{sub 2} powder approached about 10% of absolute value at 1{sigma} and a normal flow of waste stream can be maintained at least one drum per hour. On the other hand, in an effort to ease the nuclear material accounting for and control the flow of nuclear material in CANDU Fuel Fabrication Facility was analyzed to develope a model computer network interfaced with hardwares, structual design of network, computer operating system, and hardware set-up were studied to draw out the most practical network system. (Author).}
place = {Korea, Republic of}
year = {1991}
month = {Mar}
}