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June 1-6, 2014 ARIS2014. Transmutation of Long-lived Nuclear Wastes. Hiroyuki Oigawa Office of Strategic Planning (Nuclear Science and Engineering Directorate, and J-PARC Center) Japan Atomic Energy Agency. Background. Concern to radioactive waste management has been increasing in Japan.

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transmutation of long lived nuclear wastes
June 1-6, 2014

ARIS2014

Transmutation of Long-lived Nuclear Wastes

Hiroyuki Oigawa

Officeof Strategic Planning (Nuclear Science and Engineering Directorate, and J-PARC Center)

Japan Atomic Energy Agency

background
Background
  • Concern to radioactive waste management has been increasing in Japan.
  •  Transmutation technology for long-lived nuclides is drawing the attention from public, media and politicians.
  • JAEA (former JAERI and PNC/JNC) has been studying this technology for more than 20 years.
  • The Ministry of Education, Culture, Sports Science and Technology (MEXT) in Japan has launched a Working Party to review Partitioning and Transmutation Technology in August, 2013, and issued an interim report in November, 2013.
slide3
Major Long-lived Nuclides in Spent Nuclear Fuel

Fission products (FP)

Trans-uranic elements (TRU)

Actinides

Minor actinides (MA)

Dose Coefficient:

Committed dose (Sv) per unit intake (Bq), indicating the magnitude of influence of radioactivity to human body. α-activity is more influential than β,γ-activity.

partitioning and transmutation p t
Partitioning and Transmutation (P&T)

Spent fuel

Reprocessing

Recycle

U、Pu

Geological disposal (Glass waste form)

FP、MA

Conventional scheme

P&T technology

MA(Np, Am, Cm)

Transmutation by ADS and/or FR

PGM(Ru, Rh, Pd)

Utilization and/or disposal

Partitioning(Example)

Geological disposal after cooling and/or utilization (Calcined waste form)

Heat generator (Sr, Cs)

Geological disposal (high-density glass waste form)

Remaining elements

MA: Minor Actinides

FP: Fission Products

PGM: Platinum Group Metal

FR: Fast Reactor

ADS: Accelerator Driven System

reduction of radiological toxicity by p t
Reduction of Radiological Toxicity by P&T

Radiological Toxicity: Amountof radioactivity weighted by dose coefficient of each nuclide.

  • Normalized by 1t of spent fuel.
  • 9t of natural uranium (NU) is raw material of 1t of low-enriched uranium including daughter nuclides.

Spent fuel (1t)

High-level waste

MA transmutation

Natural uranium (9t)

Radiological toxicity (Sv)

  • Time period to decay below the NU level:
  • Spent fuel 100,000y  ↓
  • High-level waste 5,000y  ↓
  • MA transmutation 300y

Reduction

Reduction

Time after reprocessing (Year)

slide6
Howto Transmute MA and LLFP

Mo-102

(T1/2=11min.)

Tc-102

(T1/2=5s)

Ru-102

(stable)

Example of fission reaction of MA

β-ray

β -ray

Np-237

(T1/2=2.14M yr.)

Fission reaction

(n, f)

Neutron

Note: 10% or less of FPs are Long-lived ones.

Fast neutrons (> 1MeV)

High energy neutrons (> 10MeV)

Neutron

β -ray

β -ray

I-133

(T1/2=21hr.)

Xe-133

(T1/2=5d)

Cs-133

(stable)

Thermal neutrons

T1/2:Half life

Example of (n, 2n) reaction of LLFP

Example of capture reaction of LLFP

Te-125

(stable)

Sb-125

(T1/2=2.8yr.)

Sn-125

(T1/2=9.6d)

Sn-126

(T1/2=230k yr.)

Xe-130

(stable)

I-130

(T1/2=12hr.)

I-129

(T1/2=15.7M yr.)

Capture reaction

(n, γ)

(n, 2n) reaction

Neutron

Neutron

Β-ray

Β-ray

Β-ray

slide7
Cross Sections of Neutron-induced Reaction :

Am-241

Total

Scattering

Capture

Fission

inelastic

  • Chain reactions of fission by fast neutrons are advantageous for transmutation of MA.
slide8
Examples of “Reduced Half-life”

“Reduced Half-life” can be written as T1/2 = ln2 / (φ·σ ) , if there isno competitive reaction nor production reaction, where φ is neutron flux and σ is reaction cross section.

Condition of realistic transmutation: φ·σ >1015(barn/cm2/s)

slide9
Accelerator Driven System (ADS) for MA Transmutation

Proton beam

Max.30MW

Super-conducting LINAC

100MW

To accelerator

800MW

170MW

Fission energy

To grid

Spallation target (LBE)

270MW

MA: Minor Actinides

LBE: Lead-Bismuth Eutectic

Power generation

Transmutation by ADS

MA-fueled LBE-cooled subcritical core

Utilizing chain reactions in subcritical state

Proton

Spallation target

Fission neutrons

Fast neutrons

  • Characteristics of ADS:
  • Chain reactions stop when the accelerator is turned off.
  • LBE is chemically stable.
  •  High safety can be expected.
  • High MA-bearing fuel can be used.MA from 10 LWRs can be transmuted.

Short-lived or stable nuclides

Long-lived nuclides (MA)

slide10
ADS Proposed by JAEA
  • Proton beam : 1.5GeV
  • Spallation target : Pb-Bi
  • Coolant : Pb-Bi
  • Max. keff= 0.97
  • Thermal output : 800MWt
  • MA initial inventory : 2.5t
  • Fuel composition :
    • (MA +Pu)Nitride + ZrN
  • Transmutation rate :
    • 10%MA / Year
  • 600EFPD, 1 batch

Conceptual view of 800 MWth LBE-cooled ADS

components of double strata fuel cycle concept
Components of Double-strata Fuel Cycle Concept

U [752t/y]

Pu [8t/y]

Scope of P&T

Partitioningprocess

Fission Products (FP) [39t/y]Minor Actinides (MA) [1t/y]

Reprocessing

Spent fuel

[800t/y]

Dedicated

transmutation fuel

Fuel fabricationprocess

Minor actinides (MA)

Remaining

elements

PGM

Sr-Cs

[1t/y]

[8t/y]

[4t/y]

[5t/y]

AcceleratorDriven System(ADS)

[30t/y]

Transmutation cycle

[7t/y]

Optimization by utilization /

Disposal after cooling

Recovered actinides

Spent fuel

[1t/y]

Reprocessing

Fission products

Final disposal

[8t/y]

PGM: Platinum Group Metal

slide12
Technical Issues for ADS

J-PARC: Japan Proton Accelerator Research Complex

TEF-P: Transmutation Physics Experimental Facility

TEF-T: ADS Target Test Facility

SC-LINAC: Superconducting LINAC

  • Accelerator
  • R&D of SC-LINAC
  • Reliability Assessment
  • Construction and operation of J-PARC accelerator
  • R&D of Pb-Bi technology

Construction of TEF-T in J-PARC

  • Structure
  • Spallation Target, Material
  • Operation of Pb-Bi system
  • Design study on reactor vessel, beam duct, quake-proof structure, etc.
  • Experiments in existing facilities and analyses

Construction of TEF-P in J-PARC

  • Fuel
  • Fabrication, irradiation and reprocessing tests
  • Reactor Physics
  • Control of Subcritical System
slide13
Reliability of Accelerator

Number of beam trips per year (7,200 hours)

  • We are comparing the trip rate estimated from data of existing accelerators and the maximum acceptable trips to keep the integrity of the ADS components.
  • Short beam trip (<10s) can meet the criteria.
  • Longer beam trip should be decreased by:
    • Reducing the frequency of trips and
    • Reducing the beam trip duration

Acceptable trip rate

Beam trip rate (times/year)

Estimation from experiences

0-10s 10s – 5min. >5min.

Beam trip duration

slide14
Design of Beam Window

Temperature

Outer surface

Temperature

Of beam window

  • Beam window is subjected to severe conditions:
    • High temperature
    • Corrosion and erosion by LBE
    • Pressure difference between vacuum and LBE (~0.8MPa)
    • Irradiation by protons and neutrons
  • Temperature at the outer surface of the window can be less than 500ºC.
  • Buckling failure can be avoided by a factor of safety (FS)=3.
  • The life time of the beam window should be evaluated from viewpoints of corrosion and irradiation.  necessity of irradiation data base.
slide15
Accuracy of Neutronics Design

Benchmark calculation for 800MWt ADS for BOC and EOC.(Left: Comparison between JENDL-4.0 and JENDL-3.3, Right: Nuclide-wise contribution for differences in k-eff)

  • There is 2% difference in k-eff between JENDL-4.0 and JENDL-3.2, which is too large to design ADS. necessity of integral validation of nuclear data
slide16
Japan Proton Accelerator Research Complex:J-PARC

Hadron Experimental Facility

Jan. 28, 2008

50 GeV Synchrotron

Materials and Life Science Experimental Facility

To neutrino detector

3 GeV Synchrotron

Site for Transmutation Experimental Facility

LINAC

slide17
Transmutation Experimental Facility (TEF)

of J-PARC

Transmutation Physics Experimental Facility: TEF-P

ADS Target Test Facility:TEF-T

Purpose: To investigate physics properties of subcritical reactor with low power, and to accumulate operation experiences of ADS.

Licensing: Nuclear reactor: (Critical assembly)

Proton beam: 400MeV-10W

Thermal power: <500W

Purpose: To research and develop a spallation target and related materials with high-power proton beam.

Licensing: Particle accelerator

Proton beam: 400MeV-250kW

Target: Lead-Bismuth Eutectic (LBE, Pb-Bi)

Multi-purpose

Irradiation Area

Critical Assembly

10W

Pb-Bi Target

250kW

Proton Beam

slide18
International Collaboration with MYRRHA

ADS without MA fuel(LBE coolant, Accelerator, Operation of ADS)

Power

ADS Transmutation plant

30MW-beam,800MWth

 ・Transmute 250kg of MA annually

Experimental ADSMYRRHA

~2.4MW-beam, 50~100MWth

 ・Engineering feasibility of ADS and fuel irradiation

Reactor physics of MA transmutation system and material development for spallation target material

Advanced material for beam window

TEF in J-PARC250kW-beam

 ・LBE target technology

 ・Reactor physics of transmutation system

Basic research (LBE loop test, KUCA experiments)

year

2050

2010

2020

2030

slide19
Working Party to Review Partitioning and Transmutation Technology
  • The Ministry ofEducation, Culture, Sports Science and Technology (MEXT) in Japan has launched a Working Party to review Partitioning and Transmutation Technology in August, 2013.
  • An interim report was issued in November, 2013.
  • Key Descriptions:
  • To reduce the burden of HLW management, it is expected that flexibility in future political decision is extended by showing possibilities of new concepts of back-end with high social receptivity.
  • The ADS Target Test Facility (TEF-T) is being proposed under J-PARC to verify the feasibility of the beam window. It is appropriate to shift the R&D of the facility to the next stage.
  • The Transmutation Physics Experimental Facility (TEF-P) is being proposed under J-PARC to overcome difficulties in reactor physics issues such as for a subcritical core and an MA-loaded one. Since this facility is proposed as a nuclear reactor, the safety review by the new regulation is to be applied. With taking care of this point, it is appropriate to shift the R&D of the facility to the next stage.
  • For MYRRHA Program, it is appropriate to proceed with negotiation about JAEA’s participation at a reasonable level and mutual collaboration with Belgium and other relevant countries.
  • Progress of the development should be checked according to its stage.
slide20
Concluding Remarks
  • ADS provides us a possibility to flexibly cope with the waste management in various situations of nuclear power.
  • R&D on ADS and its compact fuel cycle are under way in JAEA, and we are proposing the Transmutation Experimental Facility as the Phase-II of J-PARC.
  • To overcome various technical challenges for this technology, the international collaborationis of great importance.
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