skip to main content
OSTI.GOV title logo U.S. Department of Energy
Office of Scientific and Technical Information

Title: Dose Rate Calculation of TRU Metal Ingot in Pyroprocessing - 12202

Abstract

Spent fuel management has been a main problem to be solved for continuous utilization of nuclear energy. Spent fuel management policy of Korea is 'Wait and See'. It is focused on Pyro-process and SFR (Sodium-cooled Fast Reactor) for closed-fuel cycle research and development in Korea. For peaceful use of nuclear facilities, the proliferation resistance has to be proved. Proliferation resistance is one of key constraints in the deployment of advanced nuclear energy systems. Non-proliferation and safeguard issues have been strengthening internationally. Barriers to proliferation are that reduces desirability or attractiveness as an explosive and makes it difficult to gain access to the materials, or makes it difficult to misuse facilities and/or technologies for weapons applications. Barriers to proliferation are classified into intrinsic and extrinsic barriers. Intrinsic barrier is inherent quality of reactor materials or the fuel cycle that is built into the reactor design and operation such as material and technical barriers. As one of the intrinsic measures, the radiation from the material is considered significantly. Therefore the radiation of TRU metal ingot from the pyro-process was calculated using ORIGEN and MCNP code. (authors)

Authors:
 [1];  [2]
  1. Department of Nuclear and Quantum Engineering, Korea Advanced Institute of Science and Technology, 335 Gwahangno, Yuseong-gu, Daejeon 305-701 (Korea, Republic of)
  2. Khalifa University of Science, Technology and Research (KUSTAR), Abu Dhabi Campus, PO.Box 127788, Abu Dhabi (United Arab Emirates)
Publication Date:
Research Org.:
WM Symposia, 1628 E. Southern Avenue, Suite 9-332, Tempe, AZ 85282 (United States)
OSTI Identifier:
22293498
Report Number(s):
INIS-US-14-WM-12202
TRN: US14V1153115022
Resource Type:
Conference
Resource Relation:
Conference: WM2012: Waste Management 2012 conference on improving the future in waste management, Phoenix, AZ (United States), 26 Feb - 1 Mar 2012; Other Information: Country of input: France; 4 refs.
Country of Publication:
United States
Language:
English
Subject:
12 MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; 61 RADIATION PROTECTION AND DOSIMETRY; DOSE RATES; FUEL CYCLE; MANAGEMENT; NUCLEAR FACILITIES; PROLIFERATION; SAFEGUARDS; SODIUM COOLED REACTORS; SPENT FUELS

Citation Formats

Lee, Yoon Hee, and Lee, Kunjai. Dose Rate Calculation of TRU Metal Ingot in Pyroprocessing - 12202. United States: N. p., 2012. Web.
Lee, Yoon Hee, & Lee, Kunjai. Dose Rate Calculation of TRU Metal Ingot in Pyroprocessing - 12202. United States.
Lee, Yoon Hee, and Lee, Kunjai. Sun . "Dose Rate Calculation of TRU Metal Ingot in Pyroprocessing - 12202". United States.
@article{osti_22293498,
title = {Dose Rate Calculation of TRU Metal Ingot in Pyroprocessing - 12202},
author = {Lee, Yoon Hee and Lee, Kunjai},
abstractNote = {Spent fuel management has been a main problem to be solved for continuous utilization of nuclear energy. Spent fuel management policy of Korea is 'Wait and See'. It is focused on Pyro-process and SFR (Sodium-cooled Fast Reactor) for closed-fuel cycle research and development in Korea. For peaceful use of nuclear facilities, the proliferation resistance has to be proved. Proliferation resistance is one of key constraints in the deployment of advanced nuclear energy systems. Non-proliferation and safeguard issues have been strengthening internationally. Barriers to proliferation are that reduces desirability or attractiveness as an explosive and makes it difficult to gain access to the materials, or makes it difficult to misuse facilities and/or technologies for weapons applications. Barriers to proliferation are classified into intrinsic and extrinsic barriers. Intrinsic barrier is inherent quality of reactor materials or the fuel cycle that is built into the reactor design and operation such as material and technical barriers. As one of the intrinsic measures, the radiation from the material is considered significantly. Therefore the radiation of TRU metal ingot from the pyro-process was calculated using ORIGEN and MCNP code. (authors)},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {2012},
month = {7}
}

Conference:
Other availability
Please see Document Availability for additional information on obtaining the full-text document. Library patrons may search WorldCat to identify libraries that hold this conference proceeding.

Save / Share: