The license application for the STACY modification has been under safety
review. The first criticality experiment in the modified STACY is scheduled for
2018. The modified STACY will provide benchmark data on criticality safety for
fuel debris to validate the new criticality control measures applicable to the
Fukushima Daiichi Nuclear Power Stations.
Open Access This chapter is distributed under the terms of the Creative Commons Attribution
Noncommercial License, which permits any noncommercial use, distribution, and reproduction in
any medium, provided the original author(s) and source are credited.
References
1. Tokyo Electric Power Company, Inc. (2012) Fukushima nuclear accident analysis report
2. Nuclear Emergency Response Headquarters, Council for the Decommissioning of TEPCO’s
Fukushima Daiichi Nuclear Power Station (2013) Mid- and-long-term roadmap towards the
decommissioning of TEPCO’s Fukushima Daiichi nuclear power station unit 1–4
3. Stratton WR (1987) Review of the state of criticality of the Three Mile Island unit 2 core and
reactor vessel. DOE/NCT-01. Lawrence Livermore National Laboratory
4. Izawa K et al (2012) Infinite multiplication factor of low-enriched UO 2 -concrete system.
J Nucl Sci Technol 49(11):1043
5. Tonoike K et al (2013) Major safety and operational concerns for fuel debris criticality control.
In: Proceedings of the GLOBAL 2013: international nuclear fuel cycle conference, Salt Lake
City, September 29–October 3, 2013
6. Miyoshi Y (2013) STACY modification program and critical experiments using pseudo fuel
debris. Working party on nuclear criticality safety, October 11, 2013, OECD/NEA, Paris
7. Tonoike K et al (2013) Principle options of fuel debris criticality control in Fukushima Daiichi
Reactors. In: International symposium on nuclear back-end issues and the role of nuclear
transmutation technology after the accident of TEPCO’s Fukushima Daiichi Nuclear Power
Stations, Kyoto, November 28, 2013
8. Izawa K et al (2012) Feasibility study on critical experiment with fuel debris in modified
STACY. 3. Neutronic characteristics analysis of modified STACY core. In: Proceedings of the
annual meeting of AESJ, Fukui, March 19–21, 2012, E37 (in Japanese)
9. Croff AG (1980) ORIGEN2: a revised and updated version of the Oak ridge isotope generation
and depletion code. ORNL-5621. Oak Ridge National Laboratory
10. Nagaya Y et al (2005) MVP/GMVP II: general purpose Monte Carlo codes for neutron and
photon transport calculations based on continuous energy and multigroup methods. JAERI1348. Japan Atomic Energy Research Institute
11. Shibata K et al (2002) Japanese evaluated nuclear data library, version 3, revision 3: JENDL3.3. J Nucl Sci Technol 39(11):1125–1136
12. Umeda M et al (2012) Feasibility study on critical experiment with fuel debris in modified
STACY. 2. Fabrication and analyses of pseudo fuel debris at nuclear fuel usage facility in
NUCEF. In: Proceedings of the annual meeting of AESJ, Fukui, March 19–21, 2012, E36
(in Japanese)
13. Kida T et al (2013) Evaluation of nuclear characteristics and safety design examination of
modified STACY for critical experiments on fuel debris. 1. Outline of critical experiments on
fuel debris and safety design principle. In: Proceedings of the annual meeting of AESJ,
Higashi-Osaka, March 26–28, 2013, H30 (in Japanese)
268
H. Sono et al.
review. The first criticality experiment in the modified STACY is scheduled for
2018. The modified STACY will provide benchmark data on criticality safety for
fuel debris to validate the new criticality control measures applicable to the
Fukushima Daiichi Nuclear Power Stations.
Open Access This chapter is distributed under the terms of the Creative Commons Attribution
Noncommercial License, which permits any noncommercial use, distribution, and reproduction in
any medium, provided the original author(s) and source are credited.
References
1. Tokyo Electric Power Company, Inc. (2012) Fukushima nuclear accident analysis report
2. Nuclear Emergency Response Headquarters, Council for the Decommissioning of TEPCO’s
Fukushima Daiichi Nuclear Power Station (2013) Mid- and-long-term roadmap towards the
decommissioning of TEPCO’s Fukushima Daiichi nuclear power station unit 1–4
3. Stratton WR (1987) Review of the state of criticality of the Three Mile Island unit 2 core and
reactor vessel. DOE/NCT-01. Lawrence Livermore National Laboratory
4. Izawa K et al (2012) Infinite multiplication factor of low-enriched UO 2 -concrete system.
J Nucl Sci Technol 49(11):1043
5. Tonoike K et al (2013) Major safety and operational concerns for fuel debris criticality control.
In: Proceedings of the GLOBAL 2013: international nuclear fuel cycle conference, Salt Lake
City, September 29–October 3, 2013
6. Miyoshi Y (2013) STACY modification program and critical experiments using pseudo fuel
debris. Working party on nuclear criticality safety, October 11, 2013, OECD/NEA, Paris
7. Tonoike K et al (2013) Principle options of fuel debris criticality control in Fukushima Daiichi
Reactors. In: International symposium on nuclear back-end issues and the role of nuclear
transmutation technology after the accident of TEPCO’s Fukushima Daiichi Nuclear Power
Stations, Kyoto, November 28, 2013
8. Izawa K et al (2012) Feasibility study on critical experiment with fuel debris in modified
STACY. 3. Neutronic characteristics analysis of modified STACY core. In: Proceedings of the
annual meeting of AESJ, Fukui, March 19–21, 2012, E37 (in Japanese)
9. Croff AG (1980) ORIGEN2: a revised and updated version of the Oak ridge isotope generation
and depletion code. ORNL-5621. Oak Ridge National Laboratory
10. Nagaya Y et al (2005) MVP/GMVP II: general purpose Monte Carlo codes for neutron and
photon transport calculations based on continuous energy and multigroup methods. JAERI1348. Japan Atomic Energy Research Institute
11. Shibata K et al (2002) Japanese evaluated nuclear data library, version 3, revision 3: JENDL3.3. J Nucl Sci Technol 39(11):1125–1136
12. Umeda M et al (2012) Feasibility study on critical experiment with fuel debris in modified
STACY. 2. Fabrication and analyses of pseudo fuel debris at nuclear fuel usage facility in
NUCEF. In: Proceedings of the annual meeting of AESJ, Fukui, March 19–21, 2012, E36
(in Japanese)
13. Kida T et al (2013) Evaluation of nuclear characteristics and safety design examination of
modified STACY for critical experiments on fuel debris. 1. Outline of critical experiments on
fuel debris and safety design principle. In: Proceedings of the annual meeting of AESJ,
Higashi-Osaka, March 26–28, 2013, H30 (in Japanese)
268
H. Sono et al.