Development of Glovebox Cleanout Assistance Tool (BCAT) by using Distributed Source-Term Analysis (DSTA)

Nakamichi, Hideo; Beddingfield, D. H.*; Nakamura, Hironobu; Mukai, Yasunobu; Kurita, Tsutomu

Kaku Busshitsu Kanri Gakkai (INMM) Nihon Shibu Dai-31-Kai Nenji Taikai Rombunshu (CD-ROM), 9 Pages, 2010/12

The Distributed Source-Term Analysis (DSTA) technique provides user with knowledge of the location of neutron-producing materials and the magnitude of activity in the large volume to be evaluated. We aimed that this technique can be used to identify the physical location and activity of holdup in the glove box. By using relationships between source and volume determined by MCNPX calculation, we developed a Glove Box Cleanout Assistance Tool (BCAT). The tool can be applied to the operator during cleanout to increase recovered material, to decrease unmeasured inventory, and to perform the cleanout effectively in order to reduce operator radiation-exposure. In order to demonstrate the BCAT performance, neutron measurements were performed around actual glovebox environment. As a result of the analysis, not only the more concrete holdup locations and the activities that we experimentally estimate the place to recover were determined, but also the new hidden holdup could be found out. This knowledge provides new effective cleanout methodology. Consequently, it is expected that the nuclear material accountancy for entire bulk-handling facility can be improved.

Concept of a new GloveBox Cleanout Assistance Tool (BCAT) by using Distributed Source-Term Analysis (DSTA)

Nakamura, Hironobu; Beddingfield, D. H.*; Nakamichi, Hideo; Kurita, Tsutomu

Proceedings of INMM 51st Annual Meeting (CD-ROM), 9 Pages, 2010/07

The Distributed Source-Term Analysis (DSTA) technique has been used in a variety of safeguards applications to determine the location and quantity of material contained within large sample volumes. The DSTA method can provide the user with knowledge of the location of neutron-producing materials and the magnitude of the localized activity. A facility operator can use this information to identify the physical location of holdup during cleanout activities. In this paper, we present the concept of using the DSTA method as a (BCAT) that is used by operator during cleanout activities to increase recovered material and reduce facility MUF. In addition to the above effects, this BCAT concept provides that operator radiation-exposure and unmeasured inventory can be also reduced. We also present the actual powder recovering result performed in PCDF and comparison result between recovered material amount and calculated amount by BCAT.

Development of the Unattended Spent Fuel Flow Monitoring Safeguards System (UFFM) for the High Temperature Engineering Test Reactor (HTTR) (Joint research)

Nakagawa, Shigeaki; Umeda, Masayuki; Beddingfield, D. H.*; Menlove, H. O.*; Yamashita, Kiyonobu

JAEA-Technology 2007-003, 24 Pages, 2007/02

JAEA-Technology-2007-003.pdf:3.61MB

As of the safeguards approach in the HTTR facility, an unattended spent fuel flow monitor (UFFM) was applied to carry out an item counting of spent fuel blocks. The UFFM is so designed and fabricated as to be the compact and unique monitor system to verify a movement of spent fuel blocks in "difficult to access" area and reduce inspection efforts. This system consists of two detector packages, electronics and computer. One package consists of two ionization chambers and a He-3 counter. The IAEA acceptance tests were performed and it was confirmed the followings: (1) All the detectors were functioning properly to measure a spent fuel block flow. (2) The time difference between detector signals was sufficient to determine the direction of the spent fuel blocks. (3) The UFFM was useful to carry out the item counting. The UFFM was approved as the IAEA safeguards equipment in the safeguards approach in the HTTR.