Assessment report on research and development activities in post-evaluation of third medium-/long-term plan and in pre-evaluation of the fourth medium-/long-term plan on "Research and Development on High Temperature Gas-cooled Reactor and Related Heat Application Technology"

Shinohara, Masanori; Sumita, Junya; Shibata, Taiju; Hirata, Masaru

JAEA-Evaluation 2022-006, 198 Pages, 2022/11

JAEA-Evaluation-2022-006.pdf:23.34MB

Japan Atomic Energy Agency (JAEA) received a post-evaluation of the third medium-/long-term plan (from FY2015 to FY2021) and pre-evaluation of the fourth medium-/long-term plan (from FY2022 to FY2028) from the "Evaluation Committee of Research Activities for High Temperature Gas-cooled Reactor (hereinafter referred to as "HTGR") and Related Hydrogen Production Technology" (hereinafter referred to as "Evaluation Committee") which consists of specialists in the fields of evaluation subjects of HTGR and related heat application technologies. As a result, for the post-evaluation of the third medium-/ long-term plan, two of the ten technical committee members concluded a score of "S", seven members concluded "A" and one member concluded "B". The comprehensive evaluation concluded a score of "A". On the other hand, one of the two humanities and social sciences members concluded a score of "B", one members concluded "C". The comprehensive evaluation concluded a score of "B". For the pre-evaluation of the fourth medium-/long-term plan, although there were some items that several evaluation committee members rated as "needs improvement," the majority of the committee members judged the plan to be appropriate. This report describes the members of the Evaluation Committee, assessment items, assessment results and JAEA's measures following the assessment.

Assessment report on research and development activities in FY2020 activity and in prospective evaluation of third mid-to long-term plan "Research and development on high temperature gas-cooled reactor and related heat application technology"

Shinohara, Masanori; Sumita, Junya; Shibata, Taiju; Hirata, Masaru

JAEA-Evaluation 2022-001, 104 Pages, 2022/06

JAEA-Evaluation-2022-001.pdf:28.15MB

Japan Atomic Energy Agency received the annual evaluation of FY2020, the research plan of FY2021 and the prospective evaluation of the third mid- to long-term plan (from FY2015 to FY2021) from the "Evaluation Committee of Research Activities for High Temperature Gas-cooled Reactor (hereinafter referred to as "HTGR") and Related Hydrogen Production Technology" (hereinafter referred to as "Evaluation Committee") which consists of specialists in the fields of evaluation subjects of HTGR and related heat application technology. As a result, for the annual evaluation of FY2020, one of the ten technical committee members concluded a score of "S", eight members concluded "A" and one member concluded "B". The comprehensive evaluation was concluded a score of "A". On the other hand, two humanities and social sciences committee members concluded "B". For the prospective evaluation of the third mid- to long-term plan, one of the ten technical committee members concluded a score of "S", eight members concluded "A" and one member concluded "B". The comprehensive evaluation was concluded a score of "A". On the other hand, two humanities and social sciences committee members concluded "B". This report describes the members of the Evaluation Committee, assessment items, assessment results and JAEA's measures following the assessment.

Dissolution of uranium and plutonium oxide using TBP-HNO complex

Miyahara, Sachiko; *; Shiba, Masanori*; *; ; *;

JNC TN8400 2002-014, 40 Pages, 2002/05

JNC-TN8400-2002-014.pdf:1.57MB

The current technology for the selective separation of plutonium and uranium from spent nuclear fuel (MOX) using TBP-HNO complex is being developed (Powdered fuel extraction process). It is promising to simplify the reprocessing process for the selective separation because of its potential to unite the chemical processes, dissolution process using nitric acid and co-extraction process using TBP solvent, and to operate under the ambient pressure and at relatively "mild" temperature. Plutonium oxide has reported to provide slower dissolution than uranium oxide in nitric acid. In this work dissolution behaviors of plutonium into TBP-HNO complex from powdered plutonium and uranium mixed oxide were examined. The powdered MOX fuel (average particles size 10m) was prepared from PuO-O pellets by heating for 4 hours at 400C. The prepared powder was dissolved into TBP-4.74mol/L HNO complex and was stirred for 300 minutes. In the test with 6 grams of powdered MOX fuel and 20 mL of the TBP-HNO complex, the concentration of plutonium reached 0.17 mol/L and about 90 percent of plutonium was dissolved. It is experimentally confirmed plutonium was dissolved into the TBP-HNO complex from plutonium and uranium mixed oxide. The early dissolution rate was almost the same as that obtained with nitric acid solution. It is likely to predict the dissolution rate from the rate for nitric acid solution. Americium that was contained in the MOX fuel was also dissolved into the TBP-HNO complex, but was slower than plutonium.

None

; ; ; ; Wada, Koji; *; *; Suzuki, Shinji*; Shiba, Masanori*

PNC TN853 83-02, 187 Pages, 1983/08

PNC-TN853-83-02.pdf:8.34MB

no abstracts in English

Development of metal ion adsorption materials using radiation processing technology

Nakano, Masanori*; Muraki, Shinsaku*; Nishino, Toru*; Chikaishi, Naoki*; Mikami, Takashi*; Shibata, Takuya; Hoshina, Hiroyuki; Saiki, Seiichi; Ueki, Yuji; Kasai, Noboru; et al.

no journal, , 

no abstracts in English