Lots of new reports (unfortunately only in Japanese for now) have been posted on Tepco's "Mid- and Long-Term Roadmap" section (
http://www.tepco.co.jp/decommision/planaction/roadmap/index-j.html) on Feb 22 and 25.
I glanced through some of them:
http://www.tepco.co.jp/nu/fukushima-np/roadmap/images1/images1/d160225_08-j.pdf
This one presents the recently finished 3D laser-scan of the torus room of Unit 3. Acquired data to be used for the evaluation of obstacles and identification of possible water leaks.
On the page numbered 7 they give some radiation dose values, but warn that they are only estimations because the measuring device used was not a calibrated one.
Measured values were between 48.2 and 161.0 mSv/h, in general showing a decrease compared to the values measured in July 2012 (given on Page 8).
http://www.tepco.co.jp/nu/fukushima-np/roadmap/images1/images1/d160225_07-j.pdf
About the stage of the cover removal process at Reactor 1 building.
After removing the roof, they started cutting some of the twisted steel beams which hinder access.
Page numbered 4: some photos of the operating floor, before and after removing some rubble.
http://www.tepco.co.jp/nu/fukushima-np/roadmap/images1/images1/d160225_16-j.pdf
Very interesting report regarding the wide range of studies and research activities being carried out regarding technologies and procedures to be used in the decommissioning works, from investigations techniques to be used for acquiring information regarding the interior of the reactors, to methods for removing the molten debris of nuclear fuel, to procedures for treating and storing contaminated stuff.
It's very long and complex, unfortunately, so I can only mention a few points now (comments made in a hurry, might need some additions/corrections later):
- the studies are being carried out keeping in mind the summer of 2017 as the tentative deadline for proposing variants from which to select (sometime around the summer of 2018) the actual method for removing the molten nuclear fuel;
- most of the items are discussed first in general terms, then on the lower-right of the page they give specific tasks/objectives planned for fiscal 2016-2017.
- for example Page 5 of 49 (page numbers refer to what the browser or PDF reader indicates) talks about the need to know more, in general, about the properties of molten nuclear fuel / corium. The task for 2016-2017 is to compile a more complete database with such information.
- Page 7 of 49 talks about getting a better image of the interior of the PCVs. In fiscal 2016 they plan to examine the lower pedestal area of PCV of Reactor 1 from the grating placed one floor above, hoping to see the molten debris; in 2017 they plan similar investigations for the PCVs of Reactor 2 and 3;
- Page 9 of 49 is on the same subject - the state of the molted fuel inside the PCVs. Tasks for 2016-2017: develop the concept for the machine and method used to open a hole at the top of the PCV for the purpose of investigating the inside and then test and verify the machine and method on mockup.
- Page 12 of 49: in 2016: prepare a database with information on thinkable methods for retrieving the debris; evaluate their compatibility with each of the reactors based on their specifics; develop concepts of machines and methods for retrieving samples of the molten fuel;
- Page 15 of 49: in 2016: evaluation of the basic elements and feasibility of the various methods for removing the molten fuel (water submerged method / in-air method, access from the top / access from the lateral).
- Page 17 of 49: objective for 2016: evaluation of methods for preventing the corrosion of the RPV and PCV, selection of anti-corrosion agents and their evaluation.
- Page 19 of 49: resistance of the RPVs/PCVs in case of earthquakes. Identification of possible weaknesses and methods to mitigate them.
- Page 21 of 49: need to study and prepare for/prevent criticalities while handling the molten fuel. Objectives for 2016: progress regarding the methods to reduce exposure of workers to radiation, and regarding methods to monitor, detect and prevent criticalities; in 2017 a well-defined method for all these should be put together.
- Page 23 of 49: studies regarding methods for repairing the PCVs and stopping the water leaks in view of filling up the PCVs with water. Some conclusions regarding their feasibility should be obtained in 2016-2017. The discussion continues on page 25 of 49, with experimental and demonstration works in these areas.
- Page 27 of 49: studies regarding the handling and storage of removed molten fuel debris. Concepts, mockups and experimental/demonstration works scheduled to advance significantly in 2016-2017.
- Discussion of studies aimed at the storage (including long term) of the contaminated debris continues on the following pages.
Then there are a few pages containing the IRID logo (these pages deserve a more detailed look into, I will try to do it later):
- Page 35 of 49 presents the stage reached in Feb 2016 regarding the model analysis of the nuclear accident.
- Page 36 of 49: present stage information regarding the properties of molten fuel/corium
- Page 37 and 38 of 49: present stage info regarding investigation techniques/robots. Interesting, on page 38, the proposed investigation through a hole made in the RPV lid.
- Page 39 and 40 of 49: present stage / concepts regarding the removal of molten fuel debris;
- Page 41 of 49: present stage, methods for evaluating the health of the RPV / PCV (corrosion, resistance to earthquakes...)
- Page 42 of 49: management of criticalities
- Page 43 and 44 of 49: techniques and experiments for repairs to the PCV
- Page 45 of 49: transport, storage and manipulation of removed molten fuel debris
- Page 46 of 49: again present stage of studies regarding the storage of contaminated debris
- Page 47 of 49: studies on the long-term resistance of fuel bundles recovered from spent fuel pools
- Page 48 of 49: robots and remote-controlled devices for the decontamination of plant installations and surfaces
- Page 49: finally, latest info regarding techniques for pinpointing the location of the molten cores.