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Thermal durability of modified Synroc material as reactor fuel matrix

Technical Report:

Abstract

A Synroc, a polyphase titanate ceramics composed of three mineral phases (perovskite, hollandite and zirconolite), has an excellent performance of immobilization of high level nuclear waste. A working group in the Department of Hot Laboratories paid special attention to this merit and started a development study on a LWR fuel named `Waste Disposal Possible (WDP) Fuel`, which has the two functions of a reactor fuel and a waste form. The present paper mainly describes thermal durability of a modified Synroc material, which is essentially important for applying the material to a fuel matrix. The two kinds of Synroc specimens, designated `SM` as modified and `SB` as a reference, were prepared by hot-pressing and annealed at 1200degC to 1500degC for 30 min in air. Unexpected and peculiar spherical voids were observed in the specimen SM at 1400degC and 1500degC, which caused the specimen swelling. The formation of the voids depends significantly on the existence of spherical precipitates seen in the as-fabricated specimen including latent micropores with high pressure. On the other hand, the heat treatment at 1500degC formed additional new phases, designated `Phase A` for the specimen SB and `Phase X` for SM. Phase A is a decomposition product of hollandite  More>>
Authors:
Kikuchi, Akira; Kanazawa, Hiroyuki; Togashi, Yoshihiro; Matumoto, Seiichiro; Nishino, Yasuharu; Ohwada, Isao; Nakata, Masahito; Amano, Hidetoshi; Mitamura, Hisayoshi [1] 
  1. Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment
Publication Date:
Aug 01, 1994
Product Type:
Technical Report
Report Number:
JAERI-Research-94-008
Reference Number:
SCA: 220300; PA: JPN-94:011228; EDB-95:007507; SN: 95001296262
Resource Relation:
Other Information: PBD: Aug 1994
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; SYNTHETIC ROCKS; THERMAL TESTING; WATER COOLED REACTORS; MATRIX MATERIALS; FUEL ELEMENTS; HEAT TREATMENTS; TEMPERATURE RANGE 0400-1000 K; SWELLING; THERMAL DIFFUSIVITY; MELTING; MICROSTRUCTURE; 220300
OSTI ID:
10102290
Research Organizations:
Japan Atomic Energy Research Inst., Tokyo (Japan)
Country of Origin:
Japan
Language:
English
Other Identifying Numbers:
Other: ON: DE95722070; TRN: JP9411228
Availability:
OSTI; NTIS; INIS
Submitting Site:
JPN
Size:
28 p.
Announcement Date:
Jun 30, 2005

Technical Report:

Citation Formats

Kikuchi, Akira, Kanazawa, Hiroyuki, Togashi, Yoshihiro, Matumoto, Seiichiro, Nishino, Yasuharu, Ohwada, Isao, Nakata, Masahito, Amano, Hidetoshi, and Mitamura, Hisayoshi. Thermal durability of modified Synroc material as reactor fuel matrix. Japan: N. p., 1994. Web.
Kikuchi, Akira, Kanazawa, Hiroyuki, Togashi, Yoshihiro, Matumoto, Seiichiro, Nishino, Yasuharu, Ohwada, Isao, Nakata, Masahito, Amano, Hidetoshi, & Mitamura, Hisayoshi. Thermal durability of modified Synroc material as reactor fuel matrix. Japan.
Kikuchi, Akira, Kanazawa, Hiroyuki, Togashi, Yoshihiro, Matumoto, Seiichiro, Nishino, Yasuharu, Ohwada, Isao, Nakata, Masahito, Amano, Hidetoshi, and Mitamura, Hisayoshi. 1994. "Thermal durability of modified Synroc material as reactor fuel matrix." Japan.
@misc{etde_10102290,
title = {Thermal durability of modified Synroc material as reactor fuel matrix}
author = {Kikuchi, Akira, Kanazawa, Hiroyuki, Togashi, Yoshihiro, Matumoto, Seiichiro, Nishino, Yasuharu, Ohwada, Isao, Nakata, Masahito, Amano, Hidetoshi, and Mitamura, Hisayoshi}
abstractNote = {A Synroc, a polyphase titanate ceramics composed of three mineral phases (perovskite, hollandite and zirconolite), has an excellent performance of immobilization of high level nuclear waste. A working group in the Department of Hot Laboratories paid special attention to this merit and started a development study on a LWR fuel named `Waste Disposal Possible (WDP) Fuel`, which has the two functions of a reactor fuel and a waste form. The present paper mainly describes thermal durability of a modified Synroc material, which is essentially important for applying the material to a fuel matrix. The two kinds of Synroc specimens, designated `SM` as modified and `SB` as a reference, were prepared by hot-pressing and annealed at 1200degC to 1500degC for 30 min in air. Unexpected and peculiar spherical voids were observed in the specimen SM at 1400degC and 1500degC, which caused the specimen swelling. The formation of the voids depends significantly on the existence of spherical precipitates seen in the as-fabricated specimen including latent micropores with high pressure. On the other hand, the heat treatment at 1500degC formed additional new phases, designated `Phase A` for the specimen SB and `Phase X` for SM. Phase A is a decomposition product of hollandite and Phase X a reaction product of Phase A and perovskite in the spherical voids. Furthermore, additional information and thermal properties examined are presented in Appendix 1 and Appendix 2, respectively. It was recognized that the modified Synroc specimen SM had excellent thermal properties. (author).}
place = {Japan}
year = {1994}
month = {Aug}
}