Investigative report on the PVC bag burst in the contamination incident at Plutonium Fuel Research Facility; Radiolysis of organic materials and raising of internal pressure

Cause Investigation Team for the PFRF Contamination Incident

JAEA-Review 2017-038, 83 Pages, 2018/03

JAEA-Review-2017-038.pdf:11.37MB

The contaminated accident occurred at Plutonium Fuel Research Facility on June, 2017. The PVC bag packaging in a fuel storage container burst when a worker opened the lid, and a part of contents (uranium and plutonium) was spattered over the room. In order to clarify the cause of the burst, the Cause Unfolding Team collected information concerning characteristics of the contents from any past records and interview. And then we observed and analyzed the contents in a glove box. We also performed experiments on radiolysis of organic materials, degradation of PVC bag by radiation, and PVC bag burst. Based on fault tree analysis, finally we concluded that the main gas generation source was alpha radiolysis of the epoxy resin mixed with the fuel powder. We hope that the calculation procedures for the gas generation and the inner pressure transition described in this report can be useful reference for the management of fuel storage in other facilities.

Life evaluation of insulating materials for electric cable by accelerated thermal-radiation combined aging, II

Yagi, Toshiaki; Seguchi, Tadao; *; *; *

Mitsubishi Densen Kogyo Jiho, (87), p.38 - 44, 1994/04

no abstracts in English

Development of diagnostic methodology of cable degradation by a stress-strain response measurement, Part, 2

*; *; *; *; Yagi, Toshiaki; Seguchi, Tadao

DEI-91-131, p.11 - 19, 1991/12

no abstracts in English

Evaluate strength and pressure integrity of blanket first wall and necessary material data

Tanigawa, Hisashi; Gwon, H.; Kawamura, Yoshinori

no journal, , 

JAEA is developing a water-cooled ceramic breeder blanket. For the blanket strength and pressure integrity are assessed. The largest stress appears in the first wall region due to the surface heat and neutron loads. Under conditions with the thermal loads and cooling water pressure, stress in the first wall is analyzed with reference to ASME Boiler and Pressure Vessel Code. Limitations related to the primary/secondary stresses and strain are considered. Material data necessary for the assessment is summarized, and then status of preparation is studied for a structural material of reduced activation ferritic/martensitic steel, F82H. The summarized date of F82H is compared with standardized 9Cr-1Mo-V.