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Title: Shielding design and analyses of the cold neutron guide hall for the KIPT neutron source facility

Abstract

Argonne National Laboratory (ANL) of the United States and Kharkov Institute of Physics and Technology (KIPT) of Ukraine have cooperated on the development, design, and construction of a neutron source facility. The facility was constructed at Kharkov, Ukraine and its commissioning process is underway. The facility will be utilized for researches, producing medical isotopes, and training young nuclear specialists. The neutron source facility is designed with a provision to include a cryogenically cooled moderator system – a cold neutron source (CNS). This cold neutron source provides low energy neutrons, which will be utilized in scattering experiment and material structures analysis. Cold neutron guides, coated with reflective material for the low energy neutrons, will be used to transport the cold neutrons to the experimental site. The cold neutron guides would keep the cold neutrons within certain energy and angular space concentrated inside, while most of the gamma rays and high-energy neutrons are not affected by the cold neutron guides. For the KIPT design, the cold neutron guides need to extend several meters outside the main shield of the facility, and curved guides will also be used to remove the gamma and high energy neutron. The neutron guides should be installed insidemore » a shield structure to insure an acceptable biological dose in the facility hall. Heavy concrete is the selected shielding material because of its acceptable performance and cost. Shield design analysis was carried out for the CNS guide hall. MCNPX was utilized as the major computation tools for the design analysis, with neutron and gamma dose calculated separately. Weight windows variance reduction technique was also used in the shield design. The goal of the shield design is to keep the total radiation dose below the 0.5 mrem/hr guideline outside the shield boundary. After a series of iterative MCNPX calculations, the shield configuration and parameters of CNS guide hall were determined and presented in this paper.« less

Authors:
;
Publication Date:
Research Org.:
Argonne National Lab. (ANL), Argonne, IL (United States)
Sponsoring Org.:
USDOE National Nuclear Security Administration (NNSA)
OSTI Identifier:
1437858
Alternate Identifier(s):
OSTI ID: 1465739
Grant/Contract Number:  
AC02-06CH11357
Resource Type:
Published Article
Journal Name:
Nuclear Engineering and Technology
Additional Journal Information:
Journal Name: Nuclear Engineering and Technology Journal Volume: 50 Journal Issue: 6; Journal ID: ISSN 1738-5733
Publisher:
Elsevier
Country of Publication:
Korea, Republic of
Language:
English
Subject:
46 INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND TECHNOLOGY; 42 ENGINEERING; Cold Neutron Source; MCNPX; Neutron Guides; Shield Design

Citation Formats

Zhong, Zhaopeng, and Gohar, Yousry. Shielding design and analyses of the cold neutron guide hall for the KIPT neutron source facility. Korea, Republic of: N. p., 2018. Web. doi:10.1016/j.net.2018.03.016.
Zhong, Zhaopeng, & Gohar, Yousry. Shielding design and analyses of the cold neutron guide hall for the KIPT neutron source facility. Korea, Republic of. https://doi.org/10.1016/j.net.2018.03.016
Zhong, Zhaopeng, and Gohar, Yousry. Wed . "Shielding design and analyses of the cold neutron guide hall for the KIPT neutron source facility". Korea, Republic of. https://doi.org/10.1016/j.net.2018.03.016.
@article{osti_1437858,
title = {Shielding design and analyses of the cold neutron guide hall for the KIPT neutron source facility},
author = {Zhong, Zhaopeng and Gohar, Yousry},
abstractNote = {Argonne National Laboratory (ANL) of the United States and Kharkov Institute of Physics and Technology (KIPT) of Ukraine have cooperated on the development, design, and construction of a neutron source facility. The facility was constructed at Kharkov, Ukraine and its commissioning process is underway. The facility will be utilized for researches, producing medical isotopes, and training young nuclear specialists. The neutron source facility is designed with a provision to include a cryogenically cooled moderator system – a cold neutron source (CNS). This cold neutron source provides low energy neutrons, which will be utilized in scattering experiment and material structures analysis. Cold neutron guides, coated with reflective material for the low energy neutrons, will be used to transport the cold neutrons to the experimental site. The cold neutron guides would keep the cold neutrons within certain energy and angular space concentrated inside, while most of the gamma rays and high-energy neutrons are not affected by the cold neutron guides. For the KIPT design, the cold neutron guides need to extend several meters outside the main shield of the facility, and curved guides will also be used to remove the gamma and high energy neutron. The neutron guides should be installed inside a shield structure to insure an acceptable biological dose in the facility hall. Heavy concrete is the selected shielding material because of its acceptable performance and cost. Shield design analysis was carried out for the CNS guide hall. MCNPX was utilized as the major computation tools for the design analysis, with neutron and gamma dose calculated separately. Weight windows variance reduction technique was also used in the shield design. The goal of the shield design is to keep the total radiation dose below the 0.5 mrem/hr guideline outside the shield boundary. After a series of iterative MCNPX calculations, the shield configuration and parameters of CNS guide hall were determined and presented in this paper.},
doi = {10.1016/j.net.2018.03.016},
journal = {Nuclear Engineering and Technology},
number = 6,
volume = 50,
place = {Korea, Republic of},
year = {Wed Aug 01 00:00:00 EDT 2018},
month = {Wed Aug 01 00:00:00 EDT 2018}
}

Journal Article:
Free Publicly Available Full Text
Publisher's Version of Record
https://doi.org/10.1016/j.net.2018.03.016

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Works referencing / citing this record:

Extension of Monte Carlo code MCS to spent fuel cask shielding analysis
journal, January 2020

  • Mai, Nhan Nguyen Trong; Zhang, Peng; Lemaire, Matthieu
  • International Journal of Energy Research, Vol. 44, Issue 10
  • DOI: 10.1002/er.5023