In-situ determination

Slides:



Advertisements
Similar presentations
Advanced GAmma Tracking Array
Advertisements

Contributions to Nuclear Data by Radiochemistry Division, BARC
Energy deposition and neutron background studies for a low energy proton therapy facility Roxana Rata*, Roger Barlow* * International Institute for Accelerator.
K. Oishi, K. Kosako and T. Nakamura Institute of Technology, Shimizu Corporation, Japan id=17 SATIF-10.
Neutron energy spectrum from U and Th traces in the Modane rock simulated with SOURCES (full line). The fission contribution is also shown (dashed line).
Tumour Therapy with Particle Beams Claus Grupen University of Siegen, Germany [physics/ ] Phy 224B Chapter 20: Applications of Nuclear Physics 24.
Measurement and Survey Protocols Defining and Identifying Radioactive Materials.
1 Induced radioactivity in the target station and in the decay tunnel from a 4 MW proton beam S.Agosteo (1), M.Magistris (1,2), Th.Otto (2), M.Silari (2)
1 Radiation Safety Aspects of the Linear Collider B. Racky, A. Leuschner, N. Tesch Radiation Protection Group TeV Superconducting Linear Accelerator.
1 JASMIN Activation Experiments (T-972/993/994) Yoshimi Kasugai on behalf of JASMIN Activation team JASMIN Activation team Y. Kasugai, K. Oishi, H. Matsumura,
Radiation Processing Irradiation consists in exposing a product to ionizing radiation in order to preserve, modify or improve its characteristics. The.
Welcome to the CHARMS See – Tea Sunday, October 11, 2015 Release of Light Alkalis (Li, Na, K) From ISOLDE Targets Strahinja Lukić,
JAERI nuclear analyses for IFMIF T. Umetsu, M. Yamauchi and M. Sugimoto Presented by Takeo NISHITANI Japan Atomic Energy Agency (JAEA) IAEA Technical Meeting.
Radiation safety evaluation for “KAMABOKO” Main Linac Tunnel KEK-APL : T.Sanami, S.Ban KEK-ACC : A.Enomoto, M.Miyahara ILC Mechanical & Electrical Review.
Production & Measurement of Thermal Neutron at RCNP Chhom Sakborey Nguyen Thi Duyen An Tran Hoai Nam Li Chunjuan Wang Mian.
Stellenbosch University
Neutron Flux Measurement at the CYRIC T. Horiguchi and A. Ishikawa (Tohoku University) For the FPCCD group.
Authorization and Inspection of Cyclotron Facilities Design, Layout and Shielding.
Experimental Studies of Spatial Distributions of Neutrons Produced by Set-ups with Thick Lead Target Irradiated by Relativistic Protons Vladimír Wagner.
Physics Colloquium Ⅱ Shibata Laboratory OKA, Hiroki Nucleosyntheses studied with a Van de Graaff Accelerator [Contents] 1. Objective.
First radiological estimates for the HIRADMAT project H. Vincke and N. Conan 1.
SLAC Measurement Protocols for Unrestricted Release of Metals and Concrete James Liu, Jim Allan, Sayed Rokni, Amanda Sabourov Radiation Protection Department.
Authorization and Inspection of Cyclotron Facilities Radiation Fields.
1 Neutron Effective Dose calculation behind Concrete Shielding of Charge Particle Accelerators with Energy up to 100 MeV V. E Aleinikov, L. G. Beskrovnaja,
FLUKA for accelerator radiation protection –Indian perspective Sunil C Accelerator Radiation Safety Section Radiation Safety Systems Division, Bhabha Atomic.
Radiation study of the TPC electronics Georgios Tsiledakis, GSI.
Characterization of the nTOF Radioactive Waste M. Brugger, P. Cennini, A. Ferrari, V. Vlachoudis CERN AB/ATB/EET.
Summary of radiation shielding studies for MTA Muon production at the MiniBooNE target Igor Rakhno August 24, 2006.
Neutron production and iodide transmutation studies using intensive beam of Dubna Phasotron Mitja Majerle Nuclear Physics Institute of CAS Řež, Czech republic.
EURISOL DS Task meeting Orsay, 07 Janvier Preliminary shielding assessment of EURISOL Post Accelerator D. Ene, D. Ridikas. B. Rapp.
Neutron double differential distributions, dose rates and specific activities from accelerator components irradiated by 50 – 400 MeV protons F. Cerutti.
Prompt dose upstream the 12-ft concrete shielding blocks Igor Rakhno May 4, 2007.
EURISOL, TASK#5, Bucuresti, November 1 Preliminary shielding assessment of EURISOL Post Accelerator D. Ene, D. Ridikas. B. Rapp.
AlCap Analysis Discussion Analysis Steps  Protons: BG, response, unfolding Question: perform alternative fast signal analysis  Muons: BG, efficiency.
Radiation protection studies for the ESS Activation issues AD seminar Michał Jarosz , Lund.
VALIDATION OF THE FLUKA MONTE CARLO CODE FOR RESIDUAL PRODUCTION WITH 500 MeV/u AND 950 MeV/u URANIUM BEAM ON COPPER AND STAINLESS STEEL TARGET E. Kozlova.
Investigation of the proton-induced reactions on natural molybdenum.
Status of ULE-HPGe Experiment for WIMP Search in YangYang
Primary Radiation Calculation for Sun Yat-Sen Proton Hospital
Heating and radiological
Topic 6 : Atomic and Nuclear Physics.
 Usefulness of  Radiopharmaceuticals Auto   Injection System (RAIS) in the PET study Jeom jin Lim Seoul National University Hospital.
Induced-activity experiment:
Electromagnetic Spectrum
at TSL high energy neutron facility
Radioactivity – review of laboratory results
Radiopharmaceutical Production
Cross-section Measurements of (n,xn) Threshold Reactions
Radiation protection of Linac4 M. Silari Radiation Protection Group
GAMOS tutorial Shielding Exercises
BNFL Instruments, British Nuclear Fuels plc.
Very preliminary study of the random background for the BiPo detector (PhoSwich configuration) Work done by Jonathan Ferracci.
Swedish Radiation Protection Authority
DAMA Calibrations – low energy
PARTICLE FLUX CALCULATION-III
Ryuji Hosoyamada2, Hiroshi Iwase3, Hiroshi Nakashima1, and Koji Niita2
Setting of various sources A
Diproton correlation in a proton-rich Borromean nucleus 17Ne
How to stop a, b, g-rays and neutrons?
Estimation of Sensitivity to Gamma Ray point Sources above 30TeV
Korea Hydro & Nuclear Power Company Seulki Kim
Setting of various source Part II
Sheng Yang a, Yen-Wan Hsueh Liu b
Aging test of glass and MRPC
Open to the Public & Open for Business
TRANSPORTATION CASK AND CONCRETE MODULE DESIGN FOR MANAGING NUCLEAR SPENT FUEL PRODUCED IN BUSHEHR NUCLEAR POWER PLANT A.M. TAHERIAN Iran Radioactive Waste.
Change of 7Be decay rate under compression
Radioactivity – review of laboratory results
Clearance Protocol for Lead at Accelerator Facilities
Hiroshi Matsumura1 Akihiro Toyoda1 Kazuyoshi Masumoto1 Go Yoshida1
Presentation transcript:

In-situ determination In-situ determination of residual specific activity in activated concrete walls of a PET-cyclotron room In-situ determination concrete walls Hiroshi Matsumura, Akihiro Toyoda, Kazuyoshi Masumoto High Energy Accelerator Research Organization (KEK), JAPAN Toshiyuki Yagishita, Takayuki Nakabayashi, Hiroyuki Sasaki, Kazuhiro Matsumura, Yoshiyuki Yamaya Japan Environment Research Co., Ltd., JAPAN Yoshiharu Miyazaki The Medical and Pharmacological Research Center Foundation, JAPAN

Typical image of a PET-cyclotron room PET-cyclotron body Concrete walls of PET-cyclotron room Target for RI production

Typical image of a PET-cyclotron room PET-cyclotron body Activated by neutrons Concrete walls of PET-cyclotron room For accelerator decommissioning, specific activity in the concrete walls has to be determined in order to identify the contaminated part. eg. Eu-152: 0.1 Bq/g Co-60: 0.1 Bq/g Clearance limit Target for RI production Purpose of this study is to establish methodology of specific activity determination in concrete walls.

Methods of specific activity determination 1. Off-site measurement with a Ge detector after core boring Depth profile Concrete wall 2. In-situ measurement with a Ge detector Activation mapping Concrete wall 3. In-situ measurement with a NaI survey meter Easier method Concrete wall

Examination site Facility: The Medical and Pharmacological Research Center Foundation in Hakui, Ishikawa, Japan Accelerator: Purpose of use: Operation duration: Room size: Measurement: 12-MeV (0.1 mA) proton cyclotron (NKK/Oxford) Production of radiopharmaceuticals for PET ~15 years ~2 years ago Operation end: 5.6 m x 5.2 m x 2.7 mH January 2017 at empty room

Methods of specific activity determination 1. Off-site measurement with a Ge detector after core boring Depth profile Concrete wall 2. In-situ measurement with a Ge detector Concrete wall 3. In-situ measurement with a NaI survey meter Concrete wall

Core boring locations CW1 South wall CW4 CW5 East wall West wall Target CW5 East wall West wall Cyclotron Shield door CW2 North wall

Depth profile of the specific activity Turned to be decrease Constant specific activity Efficiency was calculated by ISOCS. CW1 Independent of nuclide Specific activity (Bq/g) Concrete depth (cm) FIG. Typical example of depth profile of specific activity (CW1). Attainable region of gamma rays agreed with the constant region of specific activity. Good for direct measurement at concrete surface

Methods of specific activity determination 1. Off-site measurement with a Ge detector after core boring Demerit Measurable at a few locations Concrete wall 2. In-situ measurement with a Ge detector Merit Measurable at many locations Concrete wall 3. In-situ measurement with a NaI survey meter Concrete wall

Measured locations 6.5-cm-thick Pb shield 20 locations S7(high) S4 S8(low) South wall S6 S5 S3 S2 S1 E1 W5 E2 Target W4 East wall West wall E3 W3 6.5-cm-thick Pb shield Cyclotron E4 W2 20 locations E5 W1 N2(high) N1 Shield door North wall

Specific activity distribution Eu-152 Co-60 Cs-134 Specific activity (Bq/g) Eu-154 Mn-54 Location name FIG. Distributions of specific activity Eu-152, Co-60, Cs-134, Eu-154, and Mn-54 were determined. Major nuclides are Eu-152 and Co-60. We could obtain detailed distributions of the specific activity.

Relative specific activity Eu-152/Co-60 Eu-152/Co-60 = 1.59 Co-60/Co-60 = 1.00 of each nuclide for Co-60 Specific activity ratio Co-60/Co-60 Cs-134/Co-60 Cs-134/Co-60 = 0.239 Eu-154/Co-60 = 0.165 Mn-54/Co-60 = 0.138 Eu-154/Co-60 Mn-54/Co-60 Location name The activity ratio was independent of location. Specific activity ratio of each nuclide for Co-60 was obtained. Although specific activity of Eu-152 was higher than Co-60, dose rate from Co-60 became higher than Eu-152.

Methods of specific activity determination 1. Off-site measurement with a Ge detector after core boring Concrete wall 2. In-situ measurement with a Ge detector Demerit Require great care Concrete wall 3. In-situ measurement with a NaI survey meter Merit Easier Concrete wall

Measured locations S1 S3 S2 S5 S6 W5 W3 W2 W1 E1 E3 E4 E5 Shield door Target South wall East wall West wall Cyclotron North wall E2 W4 S7(high) S4 S8(low) N2(high) N1

Contact dose rate vs specific activity of Co-60 Eu-152/Co-60 = 1.59 Co-60 specific activity (Bq/g) by Ge detector Cs-134/Co-60 = 0.239 Eu-154/Co-60 = 0.165 Mn-54/Co-60 = 0.138 Specific activity of Eu-152, Cs-134, Eu-154, and Mn-54 Measured dose rate Contact dose rate (μSv/h) by NaI survey meter FIG. Correlation curve between dose rate and specific activity Co-60 specific activity is correlated with contact dose rate by NaI survey meter.

Reproducibility of specific activity from dose rate Results determined by using Ge detector TOTAL Eu-152 Co-60 Specific activity (Bq/g) Cs-134 Eu-154 Mn-54 Location name FIG. Distributions of specific activity

Reproducibility of specific activity from dose rate Put Co-60 results estimated from dose rates TOTAL Eu-152 Co-60 Specific activity (Bq/g) Cs-134 Eu-154 Mn-54 Location name FIG. Distributions of specific activity

Reproducibility of specific activity from dose rate Put all results estimated from dose rates TOTAL Eu-152 Co-60 Specific activity (Bq/g) Cs-134 Eu-154 Mn-54 reproduced well from dose rate! Location name FIG. Distributions of specific activity

We obtained an efficient method for specific activity determination Conclusion We obtained an efficient method for specific activity determination in concrete wall of PET cyclotron.

Contribution from surrounding wall 6 No shield ~50% 4 1 3 2 6.5-cm thick Pb shield ~94% 5 Contribution ratio from each wall in gamma-ray counting. 6.5-cm thick Pb shield is important for avoiding contribution from other walls.

石膏ボード(約1.5cm厚)切断 石膏ボードはがし モルタルはがし 測定場所マーキング

Gamma-ray spectrum Eu-152 Co-60 Eu-154 Cs-134 Na-22 Mn-54