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JAEA Reports

Information materials of research and development on geological isolation of radioactive waste

Kato, Tomoko; Fujishima, Atsushi; Ueno, Kenichi; ; Notoya, Shin;

JNC-TN8450 2001-003, 203 Pages, 2001/01

JNC-TN8450-2001-003.pdf:24.69MB

We have compiled and refined the information materials to explain ENTRY (Engineering Scale Test and Research Facility) and QUALITY (Quantitative Assessment Radionuclide Migration Experimental Facility). These include information materials to show activities for research and development of radioactive waste disposal in Tokai Works such as panels of experimental equipments. This work was carried out by a working group in Waste Isolation Research Division, Waste Management and Fuel Cycle Research Center; Tokai Works in 1998$$sim$$2000. We have developed database for above information materials including typical experimental equipments of ENTRY and QUALITY. In the future, it can be easily refind in case of reconstruction of the experimental equipments. This report presents the database including the experimental equipments and several pamphlet.

JAEA Reports

Remote handling demonstration test facility for spallation target

Kaminaga, Masanori; Sasaki, Shinobu; Haga, Katsuhiro; Aso, Tomokazu; Kinoshita, Hidetaka; Kogawa, Hiroyuki; Akimoto, Atsushi*; Adachi, Junichi*; Hino, Ryutaro

JAERI-Tech 2000-060, 37 Pages, 2000/11

JAERI-Tech-2000-060.pdf:5.54MB

no abstracts in English

JAEA Reports

ComparaUve analyses on nuclear charaderistics of water-cooled breeder cores

; Sato, Wakaei*;

JNC-TN9400 2000-037, 87 Pages, 2000/03

JNC-TN9400-2000-037.pdf:3.48MB

ln order to compare the nuclear characteristics of water-cooled bleeder cores with that of LMFBR, MOX fuel cell models are established for boiling and non-boiling LWR, non-boiling HWR and sodium-cooled reactor. Frst, the comarison is made between the heterogeneous cell calculation results by SRAC and those by SLAROM. The results show some differences as for neutron energy spectrum, one-grouped cross section and conversion ratio due to the different grouped cross section library (both are based on JENDL-3.2, though) used for each code, however, the difference is acceptably small for grasping the basic characteristics of the above-mentioned cores. Second, using the SLAROM code, main core parameters such as mean neutron energy, ratio of fast neutron and $$eta$$-value, are analyzed. The comparison between the cores show that softened neutron spectrum by the scattering effect of hydrogen or heavy hydrogen increase the contribution of nuclear reaction (especially for neutron capture reaction rather than fission reaction) in lower energy region comparing with LMFBR. ln order to overcome the effect, tighter lattice than LMFBR is necessary for water-cooled cores to realize the breeding of fissile nuclides. Third, effects of Pu isotopic composition on the breeding ratio are evaluated using SRAC burnup calculation. From the results, it is confirmed that degraded Pu (larger ratio of Pu-240) show the larger breeding ratio. At last, sensitivity analyses are made for k-effective and main reaction ratios. As for k-effective, using a temporary covariance data of JENDL-3.2, uncertainty resulting from the cross sections' error is analyzed for a boiling LWR and a sodium-cooled reactor. The boiling LWR core shows larger sensitivity in lower energy region than the sodium-cooled reactor (especially for the energy region lower than 1kev), And, 18-group analysis that is considered acceptably good for LMFBR analysis, should not be enough for accurate sensitivity estimation of ...

JAEA Reports

Design of the HLW buffer

; Fujita, Tomoo; ; Iwasa, Kengo; Hasegawa, Hiroshi

JNC-TN8400 99-096, 23 Pages, 1999/12

JNC-TN8400-99-096.pdf:2.01MB

The Japan Nuclear Cycle Development Institute (JNC) has prepared a second progress report (entitled H12) on research and development for geological disposal of high-level waste (HLW) in Japan. H12 report consist of a Project Overview Report and three Supporting Reports which cover the three major fields described in the AEC Guidelines: (1)evaluation of the geological environment, (2)repository design and engineering technology, (3)performance assessment. This report is prepared to explain background information of buffer design which is descried in Supporting Report 2 (Repository Design and Engineering Technology). In buffer design of H12 report, the design requirements of the buffer are assumed and the relationship between buffer thickness and density was shown corresponding design requirement as an area map. This report describes the background information such as the numerical formulations, assumptions, engineering judgement and so on.

JAEA Reports

Design concepts for overpack

*; *; Tanai, Kenji

JNC-TN8400 99-047, 54 Pages, 1999/11

JNC-TN8400-99-047.pdf:3.16MB

This paper reports on the design process for a carbon-steel overpack as a key component in the engineered barrier system of a deep geological repository described in the 2nd progress report. The results of the research and development regarding design requirements, configuration, manufacturing and inspection of overpack are also described. The concept of a composite overpack composed of two different materials is also considered. First, the design requirements for an overpack and presume environmental and design conditions for a repository are provided. For a candidate material of carbon steel overpack, forging material is selected considering enough experience of using this material in nuclear power boilers and other components. Second, loading conditions after emplacement in a repository are set and the pressure-resistant thickness of overpack is calculated. The corrosion thickness to achieve an assigned 1000 year life time and the required thickness to prevent radiolysis of ground water which might enhance corrosion rate are also determined. As aresult, the total required thickness of a carbon-steel overpack is conservatively estimated to 190 mm. This is a reduction of about 30% from the previous estimate provided in the 1st Progress Report. Additional items that must be considered in manufacturring and operating overpacks (i.e. sealing of vitrified waste, examination of main body and sealing welding, mechanism of handling) are evaluated on the basis of current technology, specific future data needs are identified. With respect to the concept of composite overpack (i.e., an outer vessel to provide corrosion-allowance or corrosion-resistant performance and an inner vessel to provide pressure-resistance), the differences in design concepts between the carbon-steel overpack and such composite overpacks are analyzed. Future data needs and analytical capabilities with respect to overpacks are also summarized.

JAEA Reports

None

; ; ; ; ; ;

JNC-TN8520 99-002, 56 Pages, 1999/04

JNC-TN8520-99-002.pdf:4.31MB

None

JAEA Reports

None

Noda, Masaru*

JNC-TJ1400 99-035, 256 Pages, 1999/02

JNC-TJ1400-99-035.pdf:21.56MB

no abstracts in English

JAEA Reports

None

Kimura, Yoshinori*; *

PNC-TJ1064 98-003, 289 Pages, 1998/02

PNC-TJ1064-98-003.pdf:25.85MB

None

JAEA Reports

Preliminary conceptual design of target system, 1; System configuration

Hino, Ryutaro; Haga, Katsuhiro; Kaminaga, Masanori; Aso, Tomokazu; Kogawa, Hiroyuki; Ishikura, Shuichi*; *; Nakamura, Fumihito*; *; *

JAERI-Tech 97-035, 194 Pages, 1997/07

JAERI-Tech-97-035.pdf:6.83MB

no abstracts in English

JAEA Reports

None

PNC-TJ8164 97-003, 77 Pages, 1997/03

PNC-TJ8164-97-003.pdf:6.65MB

no abstracts in English

JAEA Reports

None

*; Fukui, Hiroshi*; *; *; *

PNC-TJ1216 97-009, 29 Pages, 1997/02

PNC-TJ1216-97-009.pdf:0.78MB

None

JAEA Reports

None

*; Fukui, Hiroshi*; *; *; *

PNC-TJ1216 97-008, 87 Pages, 1997/02

PNC-TJ1216-97-008.pdf:2.4MB

None

JAEA Reports

None

PNC-TJ8205 96-001, 33 Pages, 1996/02

PNC-TJ8205-96-001.pdf:4.72MB

no abstracts in English

JAEA Reports

None

*

PNC-TN9080 93-001, 25 Pages, 1992/12

PNC-TN9080-93-001.pdf:0.7MB

None

JAEA Reports

Development of the ultrasonic testing equipment for FBR; Results of R&D

; ; ; ;

PNC-TN9420 92-014, 125 Pages, 1992/11

PNC-TN9420-92-014.pdf:6.57MB

This report decribes the development of multi-array type probe for FBR steamgenerator tube. We studied integration between three kinds of probes, which were for axial flaw, for circumferential flaw and for wall thickness flaw, detecting method of accuracy locating probe and basic composition of multi-channel detector. It was comfirmed that each devices had object performance in performance test. We shall use this results to study design and manufacture of ultrasonic testing equipment for steamgenerator of FBR Monju.

JAEA Reports

Mockup test apparatus for the inspection system of steam generator tubes; Design and Manufacturing

; ; ; ;

PNC-TN9410 92-254, 76 Pages, 1992/07

PNC-TN9410-92-254.pdf:2.02MB

A verification test of the inspection system of Monju steam generator(SG) tubes will be performed in near future. Mockup Test Apparatus for the inspection system of SG tubes was manufactured and installed at Mechatronics Application Reserch Facility (MARF) in OEC. The test apparatus has the same specification, which is prepared for verification test, as Monju plant; for instance, which are dimension and material of tubes, and workability for the inspection equipment. About one hundred and forty SG tubes are radially arranged in tube sheets in Monju SG, however, three tubes, inner, center and outer one, are sellected in this test apparatus for testing of inspection system, It was verified that the test apparatus was manufactured with the same accuracy and dimension as Monju. System verification test is planned using this test apparatus.

JAEA Reports

Mock-up apparatus for preparation of plutonium fuel solution for criticality experiments at NUCEF

Sakurai, Satoshi; Hirata, Masaru; ; Usuda, Shigekazu; Abe, Jiro; ; Tachimori, Shoichi; ; Kurihara, Masayoshi; Kobayashi, Iwao

JAERI-M 90-059, 35 Pages, 1990/03

JAERI-M-90-059.pdf:1.38MB

no abstracts in English

JAEA Reports

JAEA Reports

None

*; *; Komatsu, Junji*; *

PNC-TN243 81-03, 24 Pages, 1981/10

PNC-TN243-81-03.pdf:0.6MB

None

22 (Records 1-20 displayed on this page)