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An International Spent Nuclear Fuel Storage Facility -- Exploring a Russian Site as a Prototype: Proceedings of an International Workshop (2005)
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. "Experience of Japan." An International Spent Nuclear Fuel Storage Facility -- Exploring a Russian Site as a Prototype: Proceedings of an International Workshop. Washington, DC: The National Academies Press, 2005.

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An International Spent Nuclear Fuel Storage Facility: Exploring a Russian Site as a Prototype - Proceedings of an International Workshop

indirect implication for spent nuclear fuel reprocessing and related management of its residues. Direct impacts increase difficulties of siting new nuclear facilities, including not only power plants but even nuclear fuel cycle facilities, namely final repositories of high-level radioactive waste (HLW). Both direct and indirect impacts give clear rise to the role and importance of storage of spent nuclear fuel.

In the next section recent efforts at managing spent nuclear fuel in Japan are reviewed. The paper also discusses the implications for the temporal and geographical aspects of the process.

CURRENT STATUS OF SPENT NUCLEAR FUEL MANAGEMENT IN JAPAN

Present Status of Spent Nuclear Fuel Management

Table 1 shows the recent status of spent nuclear fuel accumulation at all the nuclear power stations (NPSs) as of March 2001, reflecting changes 6 months

TABLE 1 Spent Nuclear Fuel Stored at NPSs in Japan (in metric tons of uranium)

Utility Company

NPS

Loading in Core

Fuel per Batch

SF in Store

Storage Capacity

Hokkaido

TOMARI

100

30

250(+10)

420

Tohoku

Onagawa

160

40

200(+10)

370

Tokyo

Fukushima-1

580

150

1140(+40)

2100

 

Fukushima-2

520

140

1280(+30)

1360

 

Kashiwazaki-Kariwa

960

250

1470(+100)

1890

Chubu

Hamaoka

420

110

730(+10)

860

Hokuriku

Shika

60

20

50(+20)

100

Kansai

Mihama

160

50

280

300

 

Takahama

290

100

850(+50)

1100

 

Ohi

360

120

740(+70)

1370(+530)a

Chugoku

Shimane

170

40

340(+70)

440

Shikoku

Ikata

170

60

330

980(+450)b

Kyushu

Genkai

270

100

420

1060

 

Sendai

140

50

580(+10)

900(+200)c

JAPCo

Tsuruga

140

40

440(+10)

870

 

Tokai-2

130

30

220

260

Total

4630

1330

9290(+380)

14,380(+1190)

 

aRe-racking of Units 3 and 4.

bRe-racking of Unit 3.

cRe-racking of Units 1 and 2.

SOURCE: Federation of Electric Power Companies (FEPC) (http://www.fepc.or.jp). Changes in parentheses are from September 2000.

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97
Front Matter (R1-R12)
Opening Remarks (1-2)
Handling Spent Nuclear Fuel—International Experience -- IAEA Activities in Nuclear Spent Fuel Management (3-11)
Analysis of U.S. Experience with Spent Fuel (12-19)
Problems of Spent Nuclear Fuel Management and Storage Site Selection (20-29)
Feasibility of Transmutation of Radioactive Elements (30-49)
The High Level Waste Disposal Technology Development Program in Korea (50-58)
The Use of Sodium-Cooled Fast Reactors for Effectively Reprocessing Plutonium and Minor Actinides (59-72)
Site Selection for Spent Fuel Storage and Disposal of High Level Waste -- Site Selection for Spent Fuel Storage and Disposal of High Level Waste: Experience of European Countries (73-88)
The Private Fuel Limited Liability Company National Spent Fuel Site (89-95)
Experience of Japan (96-108)
The Current Status of Spent Nuclear Fuel in Korea (109-117)
Safe Transport of Spent Nuclear Fuel and High Level Waste: International Experience (118-127)
Ensuring Nuclear and Radiation Safety During the Transport of Radioactive Materials in Russia (128-142)
Problems in Establishing an International Repository for Spent Nuclear Fuel in Russia -- Creating an Infrastructure for Managing of Spent Nuclear Fuel (143-151)
Current Status of Government Regulation of Activities Associated with the Import of Spent Nuclear Fuel into the Russian Federation Return to the Russian Federation of Irradiated Fuel Assemblies from the Institute of Nuclear Physics of the Republic of Uzbekistan (152-158)
Return to the Russian Federation of Irradiated Fuel Assemblies from the Institute of Nuclear Physics of the Republic of Uzbekistan (159-162)
Investment and International Aspects of the Problem of Spent Nuclear Fuel Management (163-165)
Creation of an Underground Repository for Spent Nuclear Fuel near the City of Zheleznogorsk (Eastern Siberia) (166-176)
Conditions for the Creation of an International Spent Nuclear Fuel Repository near the Priargunsk Mining-Chemical Production Association (City of Krasnokamensk, Chita Oblast) (177-186)
Utilization of High-Level Waste -- Types of High-Level Radioactive Wastes Formed as a Result of Dry Methods of Spent Fuel Regeneration and Technologies for their Management (187-198)
Chemical Treatment of High Level Waste for Utilization (199-207)
Immobilization of High Level Waste: Analysis of Appropriate Synthetic Waste Forms (208-224)
The Management of High-Level Radioactive Wastes from the Mayak Production Association and Plans for the Creation of an Underground Laboratory (225-239)
Creation of Underground Laboratories at the Mining-Chemical Complex and at Mayak to Study the Suitability of Sites for Underground Isolation of Radioactive Wastes (240-247)
Concluding Observations--Milton Levenson (248-250)
Appendix A: Workshop Agenda (251-256)
Appendix B: Environmental Effects of Radiation in the Russian Federation (257-259)
Appendix C: Geochemistry of Actinides During the Long-Term Storage and Disposal of Spent Nuclear Fuel (260-290)