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Title: Thermal testing of solid neutron shielding materials

Abstract

Two legal-weight truck casks the GA-4 and GA-9, will carry four PWR and nine BWR spent fuel assemblies, respectively. Each cask has a solid neutron shielding material separating the steel body and the outer steel skin. In the thermal accident specified by NRC regulations in 10CFR Part 71, the cask is subjected to an 800[degree]C environment for 30 minutes. The neutron shield need not perform any shielding function during or after the thermal accident, but its behavior must not compromise the ability of the cask to contain the radioactive contents. In May-June 1989 the first series of full-scale thermal tests was performed on three shielding materials: Bisco Products NS-4-FR, and Reactor Experiments RX-201 and RX-207. The tests are described in Thermal Testing of Solid Neutron Shielding Materials, GA-AL 9897, R. H. Boonstra, General Atomics (1990), and demonstrated the acceptability of these materials in a thermal accident. Subsequent design changes to the cask rendered these materials unattractive in terms of weight or adequate service temperature margin. For the second test series, a material specification was developed for a polypropylene based neutron shield with a softening point of at least 280[degree]F. The neutron shield materials tested were boronated (0.8--4.5%) polymers (polypropylene, HDPE,more » NS-4). The Envirotech and Bisco materials are not polypropylene, but were tested as potential backup materials in the event that a satisfactory polypropylene could not be found.« less

Authors:
Publication Date:
Research Org.:
General Atomics, San Diego, CA (United States)
Sponsoring Org.:
USDOE; USDOE, Washington, DC (United States)
OSTI Identifier:
7016274
Report Number(s):
GA-A-20770; EGG-M-92433; CONF-920905-40
ON: DE93001946; TRN: 92-038129
DOE Contract Number:
AC07-88ID12698
Resource Type:
Conference
Resource Relation:
Conference: 10. international symposium on the packaging and transportation of radioactive materials: PATRAM '92, Yokohama (Japan), 13-18 Sep 1992
Country of Publication:
United States
Language:
English
Subject:
42 ENGINEERING; 36 MATERIALS SCIENCE; SHIELDING MATERIALS; THERMAL TESTING; SPENT FUEL CASKS; BORON ADDITIONS; POLYETHYLENES; POLYPROPYLENE; TEMPERATURE RANGE 1000-4000 K; ALLOYS; BORON ALLOYS; CASKS; CONTAINERS; MATERIALS; MATERIALS TESTING; NONDESTRUCTIVE TESTING; ORGANIC COMPOUNDS; ORGANIC POLYMERS; POLYMERS; POLYOLEFINS; TEMPERATURE RANGE; TESTING; 420204* - Engineering- Shipping Containers; 360604 - Materials- Corrosion, Erosion, & Degradation

Citation Formats

Boonstra, R.H. Thermal testing of solid neutron shielding materials. United States: N. p., 1992. Web.
Boonstra, R.H. Thermal testing of solid neutron shielding materials. United States.
Boonstra, R.H. 1992. "Thermal testing of solid neutron shielding materials". United States. doi:. https://www.osti.gov/servlets/purl/7016274.
@article{osti_7016274,
title = {Thermal testing of solid neutron shielding materials},
author = {Boonstra, R.H.},
abstractNote = {Two legal-weight truck casks the GA-4 and GA-9, will carry four PWR and nine BWR spent fuel assemblies, respectively. Each cask has a solid neutron shielding material separating the steel body and the outer steel skin. In the thermal accident specified by NRC regulations in 10CFR Part 71, the cask is subjected to an 800[degree]C environment for 30 minutes. The neutron shield need not perform any shielding function during or after the thermal accident, but its behavior must not compromise the ability of the cask to contain the radioactive contents. In May-June 1989 the first series of full-scale thermal tests was performed on three shielding materials: Bisco Products NS-4-FR, and Reactor Experiments RX-201 and RX-207. The tests are described in Thermal Testing of Solid Neutron Shielding Materials, GA-AL 9897, R. H. Boonstra, General Atomics (1990), and demonstrated the acceptability of these materials in a thermal accident. Subsequent design changes to the cask rendered these materials unattractive in terms of weight or adequate service temperature margin. For the second test series, a material specification was developed for a polypropylene based neutron shield with a softening point of at least 280[degree]F. The neutron shield materials tested were boronated (0.8--4.5%) polymers (polypropylene, HDPE, NS-4). The Envirotech and Bisco materials are not polypropylene, but were tested as potential backup materials in the event that a satisfactory polypropylene could not be found.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = 1992,
month = 9
}

Conference:
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  • The GA-4 and GA-9 spent fuel shipping casks employ a solid neutron shielding material. During a hypothetical thermal accident, any combustion of the neutron shield must not compromise the ability of the cask to contain the radioactive contents. A two-phase thermal testing program was carried out to assist in selecting satisfactory shielding materials. In the first phase, small-scale screening tests were performed on nine candidate materials using ASTM procedures. From these initial results, three of the nine candidates were chosen for inclusion in the second phase of testing, These materials were Bisco Products NS-4-FR, Reactor Experiments 201-1, and Reactor Experimentsmore » 207. In the second phase, each selected material was fabricated into a test article which simulated a full-scale of neutron shield from the cask. The test article was heated in an environmental prescribed by NRC regulations. Results of this second testing phase showed that all three materials are thermally acceptable.« less
  • Two legal-weight truck casks the GA-4 and GA-9, will carry four PWR and nine BWR spent fuel assemblies, respectively. Each cask has a solid neutron shielding material separating the steel body and the outer steel skin. In the thermal accident specified by NRC regulations in 10CFR Part 71, the cask is subjected to an 800{degree}C environment for 30 minutes. The neutron shield need not perform any shielding function during or after the thermal accident, but its behavior must not compromise the ability of the cask to contain the radioactive contents. In May-June 1989 the first series of full-scale thermal testsmore » was performed on three shielding materials: Bisco Products NS-4-FR, and Reactor Experiments RX-201 and RX-207. The tests are described in Thermal Testing of Solid Neutron Shielding Materials, GA-AL 9897, R. H. Boonstra, General Atomics (1990), and demonstrated the acceptability of these materials in a thermal accident. Subsequent design changes to the cask rendered these materials unattractive in terms of weight or adequate service temperature margin. For the second test series, a material specification was developed for a polypropylene based neutron shield with a softening point of at least 280{degree}F. The neutron shield materials tested were boronated (0.8--4.5%) polymers (polypropylene, HDPE, NS-4). The Envirotech and Bisco materials are not polypropylene, but were tested as potential backup materials in the event that a satisfactory polypropylene could not be found.« less
  • {sup 3}HeD/{sup 6}LiD thermal-to-fusion (E = 14 MeV) neutron converters have been developed at the IWW-2M reactor to simulate the irradiation of structural materials in a fusion reactor. These converters increase the highest energy part of the neutron spectrum (E > 14 MeV) by {approx}10{sup 10} n/(cm{sup 2}{center_dot}s) in the reactor`s test channel ({approx}6-cm diam.), corresponding to a 14-MeV neutron fluence of {approx}2{center_dot}10{sup 16} n/cm{sup 2} per 500-hour reactor cycle. However, the high energy release (up to 1--2 kW/gr) in the converters from the {sup 6}Li(n,T){alpha} and {sup 3}He(n,T)p exothermal reactions created there can be a critical problem in conductingmore » experiments of this kind.« less
  • Abstract not provided.
  • Abstract not provided.