Personal Perspective of Strategy on Nuclear Data Activities at JAEA Tokio FUKAHORI Japan Atomic Energy Agency [email protected] 2010 Symposium

Personal Perspective of Strategy on Nuclear Data

Activities at JAEA

Tokio FUKAHORIJapan Atomic Energy Agency

[email protected]

2010 Symposium on Nuclear Data, Nov. 25-26, 2010, C-CUBE, Chikushi Campus, Kyushu University, Kasuga, Japan

2010 Symposium on Nuclear Data 2

Summary (1/2) Japan Atomic Energy Agency

The JENDL-4 has been released in this year as one of goals of the first period mid-term research plan for JAEA. In the plan for the second period, the objective is “incident energy expansion of JENDL”. The objective can be achieved by producing JENDL/HE, JENDL/PD, JENDL/PK. The target applications are , for instance, - Accelerator related applications: ADS, IFMIF, etc. - Medical applications: radiation therapies, accelerator-driven BNCT, etc. - Space engineering: error of semi-conductor, dose estimation caused by cosmic-rays, etc.

For this purpose, CCONE is planned to be improved by adding some models.


Summary (2/2) Japan Atomic Energy Agency

We never forget that the main user is nuclear energy applications. - Reactors: FR, NGLWR, innovative reactors (ex. Gen-IV) - Safety research of down-stream applications: (spent) fuel transportation, reprocessing, waste management, etc. - Material science for longer reactor operation: radiation damage - Nuclear forensics for nuclear non-proliferation

For these applications, rather common nuclear data needs are for the burn-up, activation, and PKA/DPA calculations. Some items related to nuclear data activities stand on the edge of precipice. - human resources - presence (appearing) to the stake-holders - budget (especially for nuclear data measurements)

The most urgent item is “covariance business” and this must be solved at least its direction of preparation.


Introduction Japan Atomic Energy Agency

What we have done …Comparison of Three Major Libraries

Library ENDF/B-VII.0 JEFF-3.1.1 JENDL-4.0

Developed by US EU Japan

Released Year 2006 2009 2010

No. of Nuclides 393 381 406

No. of Nuclides with Gamma-ray Data 206 139 354

No. of Nuclides with Neutron DDX 171 83 318

No. of Nuclides with Covariances 26 37 95

Main Evaluation Code(s)

GNASHEMPIRE

TALYSCCONE

POD

Purity* 60% 20% 96%* Researched by N. Iwamoto (JAEA)


Introduction Japan Atomic Energy Agency

What we will do …

The 2nd Period Mid-term Plan of JAEA (2010-2014) is

“incident energy expansion of JENDL” for nuclear data.

to produce Intermediate Energy Files

The others are

to revise general purpose file and

to update activation file.

And also …

to prepare for the next generation.


Nuclear Data Needs Japan Atomic Energy Agency

For accelerator related applications

JENDL Intermediate Energy Files

J-PARC

ADS

Steam Generator Main Pump

Primary Vessel

CoreCore Support Structure

Proton Beam

IFMIF



For material science

JENDL PKA/KERMA File

NGLWRElectric Power Output: 1.7-1.8 GWFuel: Over 5% Enriched UPlant Life Time: 80 yearShorter Construction PeriodHigher Rate of Operation Balanced with SafetyTop Level Passive and Active Safety Equipments

Balanced with EconomyEarthquake-proof Construction

HP-ABWR



For medical applications and space engineering

JENDL Intermediate Energy Files

Space ( 100 MeV)≦ Error of Semi-conductor Dose Estimation by Cosmic-ray

Medical ( 250 MeV)≦　 Radiation Therapy　 Medical RI Production

http://space.jaxa.jp/jda/p4_download_j.php?mode=search&f_id=1758



For reactor research & developments (1/2)

JENDL General Purpose FileJENDL Activation File (RI productions, FPY)Covariance Data, (d-induced data)

FBR (Monju)

NGLWR(HP-ABWR)

ABTR, SFR, EFR, GFR, LFR, ADMAB, VHTRNEA WPEC SG26 Report, p.69-77 NEA/WPEC-26 (ISBN 978-92-64-99053-1)

Innovative Reactors (GIF)

Fusion Reactor



For safety researches

JENDL General Purpose FileJENDL Activation File (RI productions, FPY)

Frontend (Nuclear Fuel Supply) ex. JCO Accident (1999.9.30)

- Criticality Safety for Handling of Resources, Processing, Storage & Transport of Fuel, etc.

Reactor (Core Characteristics) - Safely Operation by Grasping ex. Chernobyl (1986.4.26) & TMI Accident (1979.3.28)

Power Distribution, Control Rod Worth, Reactivity Coefficients, etc. - Prediction of Burn-up Characteristics - Evaluation of Delayed Neutron Effect

Down-stream of Nuclear Fuel Cycle (Spent Fuel Treatment) - Criticality Safety for Storage, Transport, Reprocessing - Shielding - Decay Heat

Backend (Nuclear Waste Management) - Evaluation of Long-term Radio-toxicity (HLW) - Clearance (LLW) down-stream


Nuclear Data Needs (for safety) Japan Atomic Energy Agency

Verification of Analyzing Method Nuclear Data Validation

Composition

Geometry

Criticality Measurement

Condition (Temperature

, etc.)

Benchmark Test

Code

Library (Nuclear Data)

keff=1Result

Criticality Safety

Experiment Calculation

The recent experiments are getting more expensive relatively than before. OECE/NEA International Criticality Safety Benchmark Evaluation Project (ICSBEP)

Criticality Safety Handbook (JAEA-Data/Code 2009-010) MVP + JENDL-3.2 keff > 0.98Critical Limit: minimum mass, size, concentration, etc. at keff = 0.98

TCA

STACY



Burn-up Credit How accurately we can predict

- the reactivity loss- the nuclides concentrations

　　 of burned fuel? Inventory

MA Generation Chain



Post Irradiation Exp. (PIE)MA Differences of Commercial Plant PIE between JENDL-3.3 and -

4.

0.5

0.6

0.7

0.8

0.9

1.0

1.1

1.2

U-2

34

U-2

35

U-2

36

U-2

38

Np-

237

Pu-

238

Pu-

239

Pu-

240

Pu-

241

Pu-

242

Am

-241

Am

-242

m

Am

-243

Cm

-243

Cm

-244

Cm

-245

Cm

-246

C/E

J ENDL-4.0

J ENDL-3.3



Down-stream Spent Fuel & CaskCriticality Safety of Current Spent Fuel Casks

- Subcritical when immersed in water- Subcritical when piled up in numbers - Neutron Absorber :

-B-SUS, B-Al, B-Resin, Cd-Alloy etc. Unirradiated Fuel

with Initial 235U enrichment

keff < 0.95 (usu.)Challenge for Burn-up Credit Selected Important Nuclides : 6FPs (CEA-France at early stage)

149Sm, 103Rh, 155Gd, 143Nd, 133Cs, 152Sm 12FPs (JAERI-Tech 2001-055)

+ 99Tc, 153Eu, 145Nd, 147Sm, 95Mo, 150Sm 15FPs (OECD BUC W.G.)

+ 151Sm, 109Ag, 101Ru 13FPs (SAND87-0151) for Casks

99Tc, 103Rh, 131Xe, 133Cs, 143Nd, 145Nd, 147Pm, 147Sm, 149Sm, 151Sm, 152Sm, 153Eu, 155Gd



Backend Clearance (= radioactive nuclide productions)Nuclides Listed in Table 2 of IAEA Safety Guideline RS-G-1.7

H-3, Be-7, C-14, F-18, Na-22,24, Si-31, P-32,33, S-35, Cl-36,38, K-42,43, Ca-45,47, Sc-46,47,48, V-48, Cr-51, Mn-51,52,52m,53,54,56, Fe-52,55,59, Co-55,56,57,58,58m,60,60m,61,62m, Ni-59,63,65, Cu-64, Zn-65,69,69m, Ga-72, Ge-71, As-73,74,76,77, Se-75, Br-82, Rb-86, Sr-85,85m,87m,89,90,91,92, Y-90,91,91m,92,93, Zr-93,95,97, Nb-93m,94,95,97,98, Mo-90,93,99,101, Tc-96,96m,97,97m,99,99m, Ru-97,103,105,106, Rh-103m,105, Pd-103,109, Ag-105,110m,111, Cd-109,115,115m, In-111,113m,114m,115m, Sn-113,125, Sb-122,124,125, Te-123m,125m,127,127m,129,129m,131,131m,132,133 ,133m,134, I-123,125,126,129,130,131,132,133,134,135 , Cs-129 ,131,132,134,134m,135,136 ,137,138, Ba-131,140, La-140, Ce-139,141,143,144, Pr-142,143,Nd-147,149, Pm-147,149, Sm-151,153, Eu-152,152m,154,155 , Gd-153,159, Tb-160, Dy-165,166, Ho-166, Er-169,171, Tm-170,171, Yb-175, Lu-177, Hf-181, Ta-182, W-181,185,187, Re-186,188, Os-185,191,191m,193, Ir-190,192,194, Pt-191,193m,197,197m, Au-198,199, Hg-197,197m,203, Tl-200,201,202,204, Pb-203, Bi-206,207, Po-203,205,207, At-211, Ra-225,227, Th-226,229, Pa-230,233, U-230,231,232,233,236,237,239,240, Np-237,239,240, Pu-234,235,236,237,238,239,240,241,242,243,244, Am-241,242,242m,243, Cm-242,243,244,245,246,247,248, Bk-249, Cf-246,248,249,250,251,252,253,254, Es-253,254,254m, Fm-254,255

Red: Nuclides considered in Japanese Clearance Regulation(+ Ca-41, Ti-44, V-49, Ga-67, Ge-68, Rb-81, Ag-108m, Ba-133, Yb-169, W-188, Au-195)

2010 Korea-Japan Joint Summer School, Jul. 26-30, 2010, Suwon, Korea 16


Physical Quantities Required to Nuclear Data

Shielding Calculation (Radiation Transport & Deep Penetration) Elastic Scattering Cross Section Elastic Scattering Angular Distribution Neutron Disappearance Cross Section Structure and Decay Data

Dose Evaluation (Linear Energy Transfer; LET) PKA & KERMA Data Charged-particle Spectra

Criticality Safety, Waste Management (HLW), etc. Fission & Capture Cross Sections Fission Yields, Decay Data Activation Cross Sections

Clearance RI Production Cross Sections, Decay Data



For nuclear forensics (Nuclear Detection)

JENDL General Purpose FileJENDL Photonuclear Data File

Neutron Interrogation Method

LIBS + RAS

Laser-Induced Breakdown Plasma + Resonance Absorption Spectroscopy

Fission Cross Section, FPY, Decay Data Photonuclear Reaction Data



What will be supplied …

JENDL Intermediate Energy FilesJENDL High Energy File (JENDL/HE)JENDL Photonuclear Data File (JENDL/PD)JENDL PKA/KERMA File (JENDL/PK) … I hope

JENDL-4.1(?) with covariance dataQA is also important.

JENDL Activation File (JENDL/A) with error data

Nuclear Model Code; CCONE planned to be improved by adding some models to expand the incident energy regionand for unknown (at this moment) user needs.



Covariance Business …

Covariance: JENDL

CCONE+KALMAN Method (mainly)

Covariance: JEFF

Total Monte-Carlo Method

Covariance: ENDF

AFCI (ex. GNEP) project (BNL, LANL) project will provide 110 covariances

Motto for covariances: ‘Might not be perfect but must be sensible’

I’d like to stress that covariance data and nuclear data qualities are the different items.








Edge of Precipice Japan Atomic Energy Agency

Crisis of Human Resources

Items for Next GenerationFission; neutron spectra, delayed neutron, FPY, etc.Evaluators for Light-mass NuclidesEvaluation Tool Maker?

Presence and Budget

Budget crisis, especially for measurement facilities

It is true that nuclear data is an item like air, however, producers cannot live on air.

Items of “Endangered Species”ENSDF (emergency!!)Resonance AnalysesThermal Scattering Law


Edge of Precipice Japan Atomic Energy Agency

What we should do ?

The international collaborations are getting more important.

Those should be considered as soon as possible so that nuclear data activity level is kept for next generations.

for Crisis of Human Resources

Nuclear Data Evaluation Collaboration with Nuclear Physics Fields

(microscopic approach?)

Fostering Talents Tutorials, Production of Textbook

Tool Production Considering TENDL-like approach


Summary (again) Japan Atomic Energy Agency

The JENDL-4 has been released in this year as one of goals of the first period mid-term research plan for JAEA. In the plan for the second period, the objective is “incident energy expansion of JENDL”. The objective can be achieved by producing JENDL/HE, JENDL/PD, JENDL/PK. For this purpose, CCONE is planned to be improved by adding some models.

The nuclear data for the burn-up, activation, and PKA/DPA calculations will be prepared for the applications of reactors, safety research, material science, nuclear forensics, etc. The urgent problems for human resources, presence to the stake-holders, and budget (especially for nuclear data measurements) should be solved for example, by efforts of the international collaborations, etc.

The most urgent item is “covariance business” and this must be solved at least its direction of preparation.


Words too many … Japan Atomic Energy Agency

What I have often heard are …

When finish to produce nuclear data files?

Is it necessary to be done by Japan?

Why do not consider the world-unified nuclear data file?Since nuclear data are a kind of physical quantities, it must converge into certain values. However, it needs much more time to be fixed.

It is necessary for proper usage of nuclear data to know about the origin and background. In the case of nuclear data being produced in abroad, it has some difficulty to see it.

Nuclear data are an important database for research and developments of nuclear applications. Target materials and kinds of nuclear data are different application by application. So new nuclear data is necessary.



What is “nuclear safety and security” ?“3S” for peaceful use of nuclear energy

Safety, Security and Safeguards

Safety = Safely Operations of Nuclear Facilitiesfor Research & Developments + Regulation

Frontend Criticality Safety Intermediate Criticality Safety, Shielding, etc.

Burn-up Credit Post Irradiation Exp. (PIE)Backend Clearance

Security = Protection of Nuclear MaterialsNuclear Detection and ForensicsPhysical Protection Non-proliferation

Safeguards = Nuclear Non-proliferation Shipper and Receiver Difference (SRD)

Burn-up Calc. Direct Measurement of Pu Amount in Spent Fuel

Identification of Nuclear Materials

down-stream

2010 Symposium on Nuclear Data27

Nuclear Security/Safeguards and Nuclear DataJapan Atomic Energy Agency

Nuclear Security = Protection of Nuclear MaterialsNuclear Detection and Forensics (Origin of Actinides)Physical Protection Non-proliferation

Safeguards = Nuclear Non-proliferation Shipper and Receiver Difference (SRD)

Burn-up Calc. Direct Measurement of Pu Amount in Spent Fuel

Identification of Nuclear Materials

Nuclear SecuritySafeguards

Nuclear Detection　 - Pu Non-destructed Measurement　 - Super Limited Isotope Analysis etc.

Prevention of Smuggling & Nuclear Terrorism

Shipper and Receiver Difference

Detect Non-declared Nuclear Activities

Nuclear Identification　 - Common Database　 - Analyzing Technology


Perspective of Nuclear Data Japan Atomic Energy Agency

Tentative Time Table of JENDL2010 2011 2012 2013 2014 2015 …..

JENDL/HE

JENDL-5?JENDL-4.x?

Eval. Light Mass Nuclides

Benchmark Test for Beta-version

of JENDL/HEand

Finalizing

Maintenance of JENDL/HE

JENDL/A-201x?

Fostering Talents & Tool Productions

Maintenance of JENDL-4

CCONE Improvement, Eval.

Eval. MA



ENDF Challenge of New Evaluation Methodology (Chadwick)Fission neutron spectra Large uncertainties for emitted neutrons En< 1 MeV & En > 5 MeV Major effort underway to perform new measurements, and developed

advanced theory predictions IAEA CRP initiated Significant impacts on criticality

Post-fission beta-delayed neutron and gamma emission Spectra are crudely represented Deficiencies impact various applications - incl. decay heat Theory advances using more microscopic approaches

Fission cross sections Fission cross sections for minor actinides often poorly known Theory predictive capability is poor Various theory and experimental programs are making progress

A=99(Mo), 147 (Sm,Nd),95Zr,140Ba for precision burn-up assessment



Experimental Facilities: JapanJAEA FNS: activation, integral, 14 MeV

Tandem: (n,xn), (n,xz), (p,x), activation, 10-30 MeVTIARA: shielding experiments, 20-90 MeVJ-PARC: fission, capture, etc.

Tohoku Dynamitron: (n,xn),(n,xz), activation, 0-20 MeVUniv. CYRIC: (n,xn), activation, integral, 20-40 MeV

KEK 12 GeV Proton Synchrotron: (p,xn)

Tokyo Peletron: capture, keV regionTech.

Osaka OKTAVIAN: (n,xn), (n,xz), integral, 14 MeVUniv. RCNP: (p,x), 400 MeV

KUR e-Linac: fission, capture, total, keV region

RIKEN RIBF: FPY, (z,p), etc.



Experimental Facilities: KoreaPohan PNF: total, capture, etc. 14 MeVKIRAM MC-50 Cyclotron: p-induced reaction, 45 MeVKIGAM VdG: neutron, 0.5-2.2MeVKAERI Electron Accelerator: material, environmental, irradiation test

neutron source14 MeV Neutron Factory: fusion, activation, 14 MeVPEFP: spallation neutron source

New Facility KoRIA

PNF KAERI Electron Accelerator

Japan Atomic Energy Agency


International Cooperation

NEA/WPEC: Collaboration for specified fieldsIAEA/INDC: CRP for general interestNRDC (IAEA): EXFOR, data collections, etc.Domestic and Regional Collaboration CSEWG, JEFF, JNDC, CNDC, etc. Asian?!Direct human relationships are also important!

Documents

Personal Perspective of Strategy on Nuclear Data Activities at JAEA Tokio FUKAHORI Japan Atomic Energy Agency [email protected] 2010 Symposium