原子核物理と応用分野の架け橋としての 核データ研究

– Study of nuclear data as crossover between

nuclear physics and applications –

RCNP/九大研究会 「ハドロン物理と原子核物理のクロスオーバー」 2013年9月4日-6日 @ 九大・箱崎キャンパス

渡辺 幸信 九州大学 大学院総合理工学研究院

Email: watanabe@aees.kyushu-u.ac.jp

1

Contents

• Introduction: Application of Nuclear Physics

• Nuclear data research activities in Japan – JENDL: Japanese Evaluated Nuclear Data Library

– Code system development: CCONE

• Recent work done by our group – Application of CDCC to nuclear data evaluation

– Application of PHITS code to microelectronics

• Summary and outlook

2

原子核物理 原子・放射線物理

宇宙開発 ・宇宙線誘起ソフトエラー

エネルギー ・核融合炉 ・革新核分裂炉システム ・ 核変換システム

医療応用 ・粒子線治療 ・放射線薬剤RI製造

加速器応用

基礎研究

粒子・イオン輸送

原子核物理に関連した応用分野

分析・材料開発 ・PIXE, RBE ・加速器質量分析 AMS ・中性子ラジオグラフィー

Particle transport in matter – Neutron –

Boltzmann equation

st

ff

m

f

t

f

coll

.v

F

rv

),,(),(),',()',(' '3

.

tfvtfvdt

f

coll

vrvrvrvvrv

0F

),,(),,( tvft vrvr

- External force:

),,( tf vr

)()(),( vrvr N・ Macroscopic cross section

- Velocity distribution function Neutron flux

vvrvrr dttR ii ),,(),(),(

- Collision term:

Reaction rate for reaction i at a certain position r and time t

Atomic density

Microscopic cross section

Nuclear data

Collect evaluate tabulate

Transport of 14-MeV neutrons

Fusion reactor

Source term

Overview of nuclear data required in nuclear energy development and advanced radiation applications

5

Fission

Fusion (≦ 20 MeV)

Medical (≦ 250 MeV p)

Accelerators

Space

109 108 107 106 105 1010 10-2 10-1 100 eV

Neutron Charged particles ( p, d, alpha, etc.)

Neutron

Fission reactors Fusion technology ADS Particle therapy Space development

How Do We Produce Nuclear Data for Applications ?

"Nuclear data evaluation" provides the most reliable data set by using - Experimental data, - Theoretical model calculations, - Statistics, etc.

Evaluated nuclear data are compiled to a numerical data set followed by a specific format, e.g., ENDF-6

These data sets are processed according to user's requirements

Radiation transport codes (e.g., MCNP, PHITS, GEANT4, FLUKA, …) 6

7

JENDL-4.0

“一本の線”を引く

Contents

• Introduction: Application of Nuclear Physics

• Nuclear data research activities in Japan – JENDL: Japanese Evaluated Nuclear Data Library

– Code system development: CCONE

• Recent work done by our group – Application of CDCC to nuclear data evaluation

– Application of PHITS code to microelectronics

• Summary and outlook

8

Evaluated Nuclear Data Library : JENDL

Ref.) K. Shibata, O. Iwamoto, T. Nakagawa, et al., "JENDL-4.0: A New Library for Nuclear Science and Engineering,“ J. Nucl. Sci. Technol.. 48(1), 1-30 (2011).

JENDL: Japanese Evaluated Nuclear Data Library

The latest version of the general purpose file : JENDL-4.0 (May 2010)

http://wwwndc.jaea.go.jp/index.html

9

Overview of JENDL-4.0

Neutron energy range : 10-5 eV to 20 MeV No. of nuclides : 406 Much emphasis was placed on the improvements of fission products and

minor actinoid data for R & D of innovative reactors, high burn-up, use of MOX fuels, and burn-up credit for backend research.

Library ENDF/B-VII.1/0 JEFF-3.1.2/1 JENDL-4.0

Developed by US EU Japan

Released Year 2011/2006 2012/2009 2010

No. of Nuclides 423/393 381/381 406

No. of Nuclides

with Gamma-ray Data 286/206 216/136 354

No. of Nuclides

With n_DDX 255/171 161/83 319

No. of Nuclides

with Covariances 190/26 36/36 95

Main Evaluation Code(s) GNASH

EMPIRE TALYS

CCONE

POD 10

Theoretical model and code development

A comprehensive code for nuclear data evaluation: CCONE Application of CDCC (Continuum Discretized Coupled-Channels)

method to the study of nuclear data Validation of reaction models implemented in PHITS code

11

Role of Theoretical Model Calculations

Theoretical model calculations are important for producing “Complete” Evaluated Nuclear Data Files （完備性）:

0 20 40 60 80 1000

500

1000

1500

56Fe(p,non)

Exp Data, EXFOR

Optical Model: A.J. Koning & J.P. Delaroche

R

p (

mb

)

Ep (MeV)

Proton reaction cross section for 56Fe

To interpolate / extrapolate to unmeasured regimes

For predictions where no measured data (e.g., unstable nuclei)

12

A comprehensive code: CCONE

• Optical model – spherical optical model

– coupled channel optical model (rotational band)

– RIPL OMP data base

• DWBA for inelastic scattering

• Pre-equilibrium two component exciton model

• Dynamical cluster emission – pickup and knockout reaction systematics by Kalbach

– Iwamoto-Harada model

• Hauser-Feshbach statistical model – channels: g, n, p, d, t, h, a, f

– width fluctuation correction

• C++ object oriented programming

target fe-56

projectile n

energy ( 1 2 5 10 20)

angle ( 10 30 90 )

nucleus fe-56 {

decay +( n ripl2-1416 )

}

input

Ref.) Osamu Iwamoto, J. Nucl. Sci. Technol. Vol. 44, 687 (2007). 13

Application of CCONE code to evaluation: JENDL-4.0

By courtesy of O. Iwamoto

Gd-158

natSn(n,g) spectra

14

From phenomenological to microscopic

• Ground state properties

• Optical potential

• Nuclear level density

• g- strength function

15

Phenomenological Macroscopic approach

Microscopic approach

Physical quantities and models necessary for nuclear reaction calculations

ACCURACY (prediction of exp.data)

RELIABILITY (Sound physics)

• Direct reaction model • Preequilibrium model • Fission model • etc.

Concern of applied physics

Concern of fundermental physics Requirement of adjustable parameters

Present status

Contents

• Introduction : Application of Nuclear Physics

• Nuclear data research activities in Japan – JENDL: Japanese Evaluated Nuclear Data Library

– Code system development: CCONE

• Recent work done by our group – Application of CDCC to nuclear data evaluation

– Application of PHITS code to microelectronics

• Summary and outlook

16

Application of CDCC to nuclear data evaluation

R

Rk0 s 7Li

n(p)

t

α

CDCC (Continuum Discretized Coupled Channels) method is an extension of the coupled channel (CC) method. Since the breakup channel includes infinite number of continuum states, and the CC equation with this kind of channel cannot be solved, so the continuum states are truncated and discretized to finite states, this is the basic assumption of CDCC method.

Breakup Continuum

state

Bound

Discretized states

Bound

Truncation value

Breakup threshold

Truncation & discretization

M. Yahiro, K. Ogata, T. Matsumoto, and K. Minomo, “The continuum discretized coupled-channels method and its applications”, Progress of Theoretical and Experimental Physics 1, 01A209-1-01A209-44 (2012).

17

In cooperation with Drs. Matsumoto, Ogata, and Yahiro

• Nucleon-induced reactions on Li • Deuteron-induced reactions

CDCC: Nucleon-induced reactions on Li

18

Lithium is an important element relevant to not only a tritium breeding material in DT fusion reactors but also a candidate for target material in the intense neutron source of IFMIF. The accurate nuclear data of nucleon induced reactions on 6,7Li are currently required for incident energies up to 150 MeV.

Li

Target

Li

Blanket

ITER IFMIF

Li(d,xn) reaction

+ t

α

7Li p(n) p(n)

+

+ + d

α

6Li p(n) p(n)

+

+

6Li and 7Li can easily break up, which is an important process and can influence all the other reaction channels significantly.

En < 14 MeV En,p < 50 MeV

19

N

7Li

t

α +

7Li*

N t α + + N

t

α +

5Li*(5He*)

N t

α +

CDCC SD

FSI

1. CDCC Method (3-body) 2. Final State Interaction Model (FSI) 3. Sequential Decay Model (SD)

7Li

N t

α + CDCC

N

6Li

α +

6Li(6Li* )

N d

α + CDCC d

Calculation models used in our analysis

SD

Total, reaction, elastic scattering for 7Li

Ref.) H. Guo, Y. Watanabe, T. Matsumoto, K. Ogata, and M. Yahiro, Phys. Rev. C 87. 024610 (2013)

JLM nucleon-nucleon interaction with adjusting normalization of real and imaginary depths

20

60.015 , E 30

( ) , for Li0.45 0.0075( 30), E 30

w

EE

E

6 7( ) 1 0.0035 , for both Li and Liv E E

21

70.012 , E 30

( ) , for Li0.36 0.0075( 30), E 30

w

EE

E

),()(),()(),( ErWEErVEErU JLMWJLMVJLM

Double-differential cross sections (DDXs)

22

p + 7Li p + 7Li* α + t

p + 7Li t + 5Li* α + p

CDCC FSI

SD SD

Proton production DDX for p+7Li Triton production DDX for p+7Li

Ref.) Hairui Guo, Yukinobu Watanabe, et al., presented at ND2013, March 4-9, 2013, NY, USA

CDCC: Deuteron-induced reactions

Complete Fusion

Incomplete Fusion

Glauber model (eikonal approx. + adiabatic approx.)

CDCC (S-matrices for d-breakup transition)

Exciton model + Hauser-Feshbach model

①Elastic Breakup (diffractive breakup)

neutron proton

deuteron

+

Target

②Stripping (inelastic breakup)

③ Statistical process Absorption

SD

LL

EP

2

Glauber

LL

STR

2

CDCC

LL

EB

2

LL

),(2

nnnn

p

nnnn

xnd

ddE

d

ddE

d

ddE

d

ddE

d

DDX of inclusive (d,xn) reaction:

Ref.) T. Ye, Y. Watanabe, et al., Phys. Rev. C 84, 054606 (2011).

IFMIF

23

Neutron sources

Deuteron elastic scattering

We demonstrate the applicability of CDCC calculations to 27Al and 58Ni target.

The CDCC calculation reproduces the experimental data as well as the optical model calculation.

• In the CDCC, the nucleon optical model potentials (OMPs) are necessary as input data.

→We use Koning and Delaroche OMPs for proton and neutron.

Ref.) A.J. Koning and J.P. Delaroche, Nucl. Phys. A 713, 231(2003).

24 Ref.) Shinsuke. Nakayama, Yukinobu Watanabe, et al., presented at ND2013, March 4-9, 2013, NY, USA

DDXs for 58Ni (d,xp) at 100 MeV

58Ni(d,xp)@100 MeV

The summation of three components reproduces both the shape and magnitude of the experimental (d, xp) spectra

better than TALYS calculation.

TALYS

Statistical Decay

(CCONE)

Neutron Stripping (Glauber)

Elastic Breakup (CDCC)

Total

25

Nuclear reaction models used in radiation transport codes

Radiation transport code : PHITS

Particle and Heavy Ions Transport System

Spallation target

Cancer therapy

Dose estimation of Cosmic rays

Ref.) K. Niita et al., PHITS: Particle and Heavy Ion Transport code System, Version 2.23, JAEA-Data/code 2010-022 2010.; http://phits.jaea.go.jp/index.html

- INC: Intra-Nuclear Cascade model - QMD: Quantum Molecular Dynamics - JAM: Hadron cascade model -GEM : Generalized Evaporation Model - etc.

Various studies of nuclear data necessary for validation of reaction models and modification of the models are now ongoing .

Nuclear reaction models implemented in PHITS

26

Application of nuclear data to microelectronics

27

Single-Event Upset (SEU)

The SEUs (Soft errors) have recently been recognized as a key reliability concern for many current and future silicon-based integrated circuit technologies.

- One of the radiation effects caused in microelectronic devices (e.g., semiconductor memory devices) used in various cosmic-ray environments

Soft Error or Soft Failure

- When a memory device is exposed to radiations, the memory state of a cell can be flipped from a 1 to a 0 or vice versa, resulting in malfunction caused by an error in a bit.

- “Transient" effect caused by a single ionizing particle

MRS Bulletin, Vol.28, No.2 (2003)

The K computer

http://www.aics.riken.jp/en/kcomputer/what.html

Physics involved in SEU phenomena

28

Size

e-h pair generation

Charge collection （drift- diffusion）

Soft-error

Device physics

Silicon

Nucleus

Elementary particle

Memory devices

Silicon Chip

Cosmic-rays

＋ - ＋ ＋

- - ＋ ＋ ＋ ＋

＋

- - -

- -

000000 000100 000000

fm

nm

mm

Nuclear Physics

Radiation physics

Cosmic-ray physics

Nuclear Reaction

Multi-physics & Multi-scale simulation

Reliability engineering JEDEC standard

10-9

10-8

10-7

10-6

10-5

10-4

10-3

10 100 1000 104

Latitude: 42.35deg. NLongitude: 288.95 deg.Altitude: 0 ft.

Press. = 1033 g/cm2

Neutrons

Total flux/cm2-yr :

Flu

x (

n/c

m2 M

eV

se

c)

Particle energy (MeV)

Neutrons = 178210

Validation of nuclear reaction models used in PHITS

Ref. of MQMD) Y. Watanabe and D. N. Kadrev, Proc.of ND2007, EDP Science, pp. 1121-1124 (2008).

Ref.) S. Abe et.al., Journal of Physics: Conference Series 312, 062004 (2011).

Recommended reaction models in PHITS code

Neutron energy range Model option

< 20 MeV “e-mode” option with JENDL-4.0

≥ 20 MeV Modified QMD(MQMD) + GEM

Production cross sections of proton and alpha from Si

Note: MQMD = QMD + surface coalescence model GEM = Generalized Evaporation Model

29

10-2

10-1

100

101

102

103

0 20 40 60 80 100

Cro

ss S

ectio

n [m

b]

Incident Energy [MeV]

natSi(n,x)

D.W.Kneff+ (1986)

e-mode (JENDL-4.0)

U.Tippawan+ (2004)S.Benck+ (2002)

F.B.Bateman+ (1999)

MQMD+GEM

INC+GEMINCL+GEM

10-2

10-1

100

101

102

103

0 20 40 60 80 100

Cro

ss S

ectio

n [m

b]

Incident Energy [MeV]

natSi(n,xp)

e-mode (JENDL-4.0)

F.L.Hassler+ (1962)

U.Tippawan+ (2004)S.Benck+ (2002)

F.B.Bateman+ (1999)

MQMD+GEM

INC+GEMINCL+GEM

Validation of nuclear reaction models used in PHITS

10-4

10-3

10-2

10-1

100

101

0 20 40 60 80 100 120 140 160 180 20010

-4

10-3

10-2

10-1

100

101

0 20 40 60 80 100 120 140 160 180 200

Exp.

INC

QMD

MQMD

Ein=175MeV, 28

Si(n,x), 20deg.

Ein=175MeV, 28

Si(n,x), 60deg.

Ein=175MeV, 28

Si(n,x), 100deg.

DD

X [

mb/

MeV

/sr

]

4He Energy [MeV]

Ein=175MeV, 28

Si(n,x), 140deg.

4He Energy [MeV]

Double-differential cross sections of alpha production

En=175 MeV En=96 MeV

30

10-12

10-10

10-8

10-6

10-4

10-2

100

102

104

106

0 20 40 60 80 100Alpha Particle Energy [MeV]

DD

X [m

b/s

r/M

eV

]

20deg.

40deg. (x10-2)

80deg. (x10-6)

60deg. (x10-4)

100deg. (x10 -8)

MQMD+GEM

INC+GEMINCL+GEM

U.Tippawan+ (2004)

natSi(n,x) @ 96 MeV

102

103

104

0 0.5 1 1.5 2

INC+GEMINCL+GEMMQMD+GEM

SE

R [F

IT/M

bit]

Collected Charge [fC]

Design Rule: 25 nm

Comparison of SERs between INC and MQMD

Monte Carlo calculations of terrestrial neutron-induced SERs for 25 nm design rule NMOSFET using Bertini-INC and MQMD

The difference between calculations reaches to about 50 % at Qc=0.6 fC.

Qc=0.6 fC

31

0.0

0.2

0.4

0.6

0.8

1.0

25 32 45 65

Fra

ction

Design Rule [nm]

H He others

まとめ と 展望

国内での核データ評価活動の現状（JENDL-4）と当研究Grの 最近の研究成果（一部、微視的核反応理論の応用）を紹介した。 Liに対する核子入射反応のCDCC解析 重陽子分解入射反応のCDCC解析 半導体ソフトエラー解析のための核反応モデル（QMDやINC）

従来の核データ評価に適用された現象論的な手法に代わり、 物理に基づく信頼性と高い予測精度の両方を兼ね備えた 核反応理論の確立が望まれている。

特に、核の個性が強い軽核に対する核データは今後さらなる改善の余地があり、核構造計算も含めて微視的核反応理論の適用が期待できる分野の１つだと考えている。

32

原子核物理 原子・放射線物理

宇宙開発 ・宇宙線誘起ソフトエラー

エネルギー ・核融合炉 ・革新核分裂炉システム ・ 核変換システム

医療応用 ・粒子線治療 ・放射線薬剤RI製造

加速器応用

基礎研究

粒子・イオン輸送

原子核物理に関連した応用分野

分析・材料開発 ・PIXE, RBE ・加速器質量分析 AMS ・中性子ラジオグラフィー

Nuclear Theories and Calculation Codes in Nuclear Data Evaluation

34

NJOY PHITS MCNP GEANT

CCONE, Talys, EMPIRE, etc

N-N interaction

Microscopic OMP

(G-matrix, RIA)

QMD, INC, etc

Phenomenological OMP

Level density

Shell model Collective model

Standard (p-p, n-p)

Nuclear structure (HFB, QRPA)

Collective levels, Enhancement factors

Transport code

Reaction model codes

Processing code

neutron ≤ 20MeV

謝 辞

35

松本 琢磨 氏 （九大院・理） 緒方 一介 氏 （阪大 RCNP） 八尋 正信 氏 （九大院・理） 安部 晋一郎 氏 （九大院・総理工） 郭 海瑞 氏 （九大院・総理工） 中山 梓介 氏 （九大院・総理工） 長岡恒平 氏 （九大院・総理工）

CDCCおよび半導体ソフトエラー研究は、以下の共同研究者

の方々の協力を得て実施されました。この場を借りて、感謝申し上げます。