Quality control and uncertainty evaluation for accountancy analysis at PFDC-JAEA

Sumi, Mika; Okazaki, Hiro; Abe, Katsuo; Kageyama, Tomio; Nakazawa, Hiroaki

Proceedings of INMM 53rd Annual Meeting (CD-ROM), 9 Pages, 2012/07

PFDC has been developing various technologies for MOX fuel production, and Pu and U isotopic composition and content of these samples are analyzed at PFDC-lab. For the analysis of MOX fuel material including raw material powders, PFDC-lab is accredited as the testing laboratory of ISO/IEC 17025 scoped for (1) Pu and U isotopic composition measurement in the nuclear fuel materials by MS and (2) Pu and U content measurement in the nuclear fuel materials by IDMS. This accreditation was granted in March 2010. While preparing for accreditation, the PFDC-lab established the capability to estimate measurement uncertainty in accordance with the GUM Guide and developed calculation program combining GUM-Workbench and Excel. This paper presents details of our quality control system and measurement uncertainty evaluation systems.

Experience on preparation of LSD spikes for MOX samples

Sumi, Mika; Abe, Katsuo; Kageyama, Tomio; Nakazawa, Hiroaki; Katchi, Tomokazu*; Murakami, Yoshiki*; Hishi, Tomoyuki*; Ai, Hironobu*

Proceedings of INMM 50th Annual Meeting (CD-ROM), 9 Pages, 2009/07

Currently, many laboratories who measure Pu and U concentration by isotope dilution mass spectrometry (IDMS) use Large Size Dried (LSD) spikes, which contain both Pu and U in individual vials. Plutonium Fuel Development Center (PFDC) prepared LSD spikes for MOX samples and has been used while LSD spikes prepared at inspection laboratories and commercially supplied are mainly aimed to measure input solution for reprocessing. Difficulties of importing reference materials are increasing though the needs of Pu reference materials are increasing. Stable securing Pu reference material is essential for facility operation and it is considered to be important to acquire technique to prepare domestic Pu reference material. Pu were prepared from MOX powder at PFDC and used for LSD spike preparation. Practical tests were performed with JNFL. Experience of preparation and utilization of LSD spike for MOX, consideration of certification method for MOX-Pu will be explained also in this paper.

Post Irradiation Examination for The FUGEN High Burn-up MOX Fuel Assembly (III) Final Report

Ikusawa,Yoshihisa; Kikuchi, Keiichi; Ozawa, Takayuki; Nakazawa, Hiroaki; Isozaki,Takao*; Nagayama, Masahiro*

JNC TN8410 2005-012, 113 Pages, 2005/08

JNC-TN8410-2005-012.pdf:15.2MB

The E09 fuel assembly was irradiated in the FUGEN from February 1990 to January 1997. The fuel assembly was the highest burn-up assembly in FUGEN and the pellet peak burn-up reached about 48 GWd/t. The E09 fuel assembly was transported to Japan Atomic Energy Research Institute (JAERI) Tokai in 2001. Post Irradiation Examinations (PIE) were started in July 2001, and all PIE items were completed by March 2005. The irradiation behavior of E09 MOX fuel was evaluated from the result of PIE. The major results are as follows; The integrity of E09 fuel assembly and fuel rods was confirmed. The corrosion behavior of ATR MOX fuel cladding was similar to that of LWR-UO2 fuel cladding. The central void was observed in outer ring samples irradiated with the maximum linear power over 45kW/m. A porous fine structure, similar to the rim structure seen in LWR-UO pellet, was observed in the circumferential region of MOX pellet and around the plutonium-rich spots. The MOX fuel properties irradiated up to ~48 GWd/t, which are pellet swelling, thermal conductivity, pellet melting temperature and diffusivity of fission gas, were similar to LWR-UO fuel properties. These results will be used for CANDU-OPTION program, which is one of Russian surplus weapon plutonium disposition programs with AECL in Canada, and available for LWR plutonium recycle program in Japan.

Post Irradiation Examination for The FUGEN High Burn-up MOX Fuel Assembly (II) Destructive Examination

Ikusawa,Yoshihisa; Kikuchi, Keiichi; Ozawa, Takayuki; Nakazawa, Hiroaki; Abe, Tomoyuki; Isozaki,Takao*; Nagayama, Masahiro*

JNC TN8410 2004-008, 106 Pages, 2004/10

JNC-TN8410-2004-008.pdf:25.96MB

The "E09" was irradiated in the FUGEN from February 1990 to January 1997, and its average burn-up reached 37.7GWd/t at the end of irradiation. In order to be irradiated up to high burn-up, this fuel assembly had the design improved by applying the fissile content with axial distribution, four UO- GdOfuel rods located with MOX fuel rods and so on. The E09 fuel assembly had been cooled in the FUGEN spent fuel pool for four years after irradiation.After that, it was transported to Japan Atomic Energy Research Institute (JAERI) Tokai in 2001.Post Irradiation Examinations (PIE) were started in July 2001 at Reactor Fuel Examination Facility in JAERI, and a part of destructive examinations(Puncture examination, Ceramography, Metallography and alpha-autoradiography) were completed in March 2003. The destructive examinations will be completed by December 2004.In this report, the data obtained from destructive examinations completed in March 2003 were summarized, and the evaluation results of irradiation performance of MOX fuel and cladding were discussed. Consequently, the MOX fuel rod integrity during irradiation was confirmed from the result of the destructive PIE. These results will be used for CANDU-OPTION program, which is one of Russian surplus weapon plutonium disposition programs with AECL in Canada, and available for LWR plutonium recycle program in Japan.

Design Report of Fuel Pins for FUJI Project among PSI, NRG and JNC

Ozawa, Takayuki; Nakazawa, Hiroaki; Abe, Tomiyuki

JNC TY8410 2003-002, 40 Pages, 2003/06

JNC-TY8410-2003-002.pdf:63.99MB

None

Post irradiation examination for the FUGEN high burn-up MOX fuel assembly (I) Nondestructive Examination

Ikusawa,Yoshihisa; ; Nakazawa, Hiroaki; ; *; Nagayama, Masahiro*

JNC TN8410 2003-004, 233 Pages, 2003/02

JNC-TN8410-2003-004.pdf:24.5MB

The irradiation examination on the fuel that was fabricated for the demonstration advanced thermal reactor (DATR), had been conducted in SGHWR in the U.K. and in FUGEN. The FUGEN High Burn-up MOX Fuel Assembly "E09" was developed for high burn-up fuel of DATR. The "E09" MOX fuel assembly was irradiated at the FUGEN from February 1990 to January 1997, and its average burn-up reached 37.7GWd/t. In order to be irradiated up to high burn-up, they had the design improved by applying the fissile content with axial distribution, four UO-GdO fuel rods and so on. The E09 fuel assembly had been cooled in the FUGEN spent fuel pool for four years after irradiation. After that, it was transported to Japan Atomic Energy Research Institute (JAERI) Tokai Research Establishment in 2001. Post Irradiation Examinations (PIE) were started in July 2001 at Reactor Fuel Examination Facility in JAERI, and the nondestructive examinations were completed in March 2002. The destructive examinations have been started in April 2002, and will be completed by March 2004. In this report, the data from nondestructive examinations will be summarized, and evaluation results of irradiation performance will be discussed. The integrity of fuel assembly during irradiation was confirmed in the nondestructive PIE. These results will be available for LWR MOX fuel program in Japan and for CANDU-OPTION program, which is one of Russian surplus weapon plutonium disposition programs with AECL in Canada.

Fabrication Drawings of Fuel Pins for FUJI Project among PSI, JNC AND NRG -Revised Version 2-

; Nakazawa, Hiroaki; ; Nagayama, Masahiro*

JNC TY8410 2002-002, 46 Pages, 2002/10

JNC-TY8410-2002-002.pdf:0.18MB

None

Fabrication Drawings of Fuel Pins for FUJI Project among PSI, JNC and NRG; Revised version (Joint research))

Ozawa, Takayuki; Nakazawa, Hiroaki; Abe, Tomoyuki; Nagayama, Masahiro*

JNC TY8410 2001-001, 42 Pages, 2001/10

JNC-TY8410-2001-001.pdf:1.43MB

None

Development of database system on MOX fuel for water reactors (I)

; *; Nakazawa, Hiroaki;

JNC TN8410 2000-012, 239 Pages, 2000/04

JNC-TN8410-2000-012.pdf:17.15MB

JNC has been conducted a great number of irradiation tests to develop MOX fuels for Advanced Thermal Reactor and Light Water Reactors. In order to manage irradiation data consistently and to effectively utilize valuable data obtained from the irradiation tests, we commenced construction of database system on MOX fuel for water reactors in 1998 JFY. Collection and selection of irradiation data and relevant fuel fabrication data, design of the database system and preparation of assisting programs have been finished and data registration onto the system is under way according to priority at present. The database system can be operated through the menu screen on PC. About 94,000 records of data on 11 fuel assemblies in total have been registered onto the database up to the present. By conducting registration of the remaining data and some modification of the system, if necessary, the database system is expected to complete in 2000 JFY. The completed database system is to be distributed to relevant sections in JNC by means of CD-R as a media. This report is an interim report covering 1998 and 1999 JFY, which gives the structure explanation and users manual concerning to the prepared database up to the present.

Preparation and evaluation of reference materials (LSD spikes), 1; Preparation and testing

Katchi, Tomokazu*; Kushigeta, Yoshiyuki*; Murakami, Yoshiki*; Hishi, Tomoyuki*; Ai, Hironobu*; Takamatsu, Mai*; Ebisawa, Noriyuki; Sumi, Mika; Abe, Katsuo; Kageyama, Tomio; et al.

no journal, , 

Standard material which called Large Size Dried (LSD) spikes is required for Plutonium and Uranium measurement by Isotope Dilution Mass Spectrometry (IDMS). Collaboration work between JAEA and JNFL is performed to validate efficient use of standard material (primary) and to evaluate the effectivity of the Pu which separated and purified from MOX stored at JAEA. Preparation of the LSD spikes at JAEA and evaluation with actual samples with remote operation systems at JNFL will be presented.