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4. Core with zirconium hydride in fuel elements For enhancement of plutonium burn-up rate a moderated zone containing zirconium hydride in the fuel element may be used. Zirconium hydride is a good moderator and has good inert properties. Application of zirconium hydride moderated zones in fast reactors were considered in papers [8-9]. We have considered the reactor core with fuel elements containing zirconium hydride layer located in the gap between the fuel pellet and steel cladding or around the steel cladding. All dimensions of the fuel pin were taken as in the reference core. Due to the shifting of the neutron spectrum to the thermal energy region more than 70% of the plutonium burn-up events occurs in the thermal energy region. The use of the fuel elements with zirconium hydride and plutonium enrichment of 20%-23% permits to burn up about B Pu = 25 kg/FPY (at the P r = 80 MW) of plutonium at the average power density in the fuel of q f = 227 W/cc. There are two possible arrangements of zirconium hydride layer in fuel element: (1) HZr arranged abutting to the outer surface of the steel cladding, and (2) HZr layer may be arranged in the gap between the fuel pellet and the steel cladding of the fuel element. In Table 2 results of computations of the reactor core with different arrangement of HZr layer in fuel element are presented. Burn-up rate of plutonium in fuel elements with HZr layer (∆d 2 (HZr) ≈ 0.045 ÷ 0.072 cm) arranged abutting to the outer surface of fuel pin is equal to B Pu = 24.8 kg/FPY, while B Pu = 21.6 kg/FPY in the core with HZr layer (∆d 1 (HZr) ≈ 0.035 cm) arranged inside the fuel element. The average power density is equal to q f = 228 W/cc (21.8 W/g) in fuel elements with HZr layer arranged abutting to the outer diameter of fuel cladding, and q f = 258W/cc (24.7 W/g) in fuel elements containing HZr layer inside fuel element. Table 2. Fuel elements containing H 2 Zr cladding arranged in different positions: (1) Abutting to the outer diameter of the steel cladding. (2) In the gap between the fuel pellet and the steel cladding. Parameter 23.225% Reference core Plutonium enrichment, % 20.0% 23.2% 55% Position of HZr – (1) (2) (1) (2) r fuel , cm 0.09 0.09 0.08 0.09 R fuel , cm 0.357 0.357 0.33 0.301 r clad , cm 0.3685 0.3685 0.3685 0.3685 R clad , cm 0.425 0.425 0.425 0.425 k eff 0.9839(5) 0.9831(5) 0.9811(6) 0.9828(6) k s 0.980 0.982 0.981 0.984 I p (mA) 1.67 1.51 1.61 1.41 q f (W/g) 21.98 21.82 24.73 31.00 k v = q max /q f 1.35 1.37 1.32 – B Pu , (kg/FPY) 13.7 24.8 21.6 33.2 Fuel element with plutonium enrichment 55% and two moderated zones of zirconium hydride is also considered. The first HZr zone is arranged abutting to the outer diameter of fuel element (the thickness of the layer is equal to 0.07 cm) and the second zone is arranged in the gap between the fuel 812
pellet and the steel cladding. In order for the effective multiplication factor to be equal to k eff = 0.984, a small fraction (3%) of natural Eu absorber was added to internal zirconium hydride layer. In this scheme the plutonium incineration rate is equal to B Pu = 33.2 kg/PFY (P r = 80 MW) and the average power density in the fuel is equal 31.0 W/g. 5. Production of 210 Po from 209 Bi in the cores with B 4 C and zirconium hydride Production of 210 Po in the lead-bismuth eutectic was calculated for the reference core in the ENEA report [8]. It was indicated that the main contribution to the production of 210 Po give neutrons with energy below 20 MeV in the reaction of neutron capture: 209 Bi(n,γ)→ 210g Bi(T 1/2 = 5.013 days)→ 210 Po The fraction α 210g of the cross-section value for 210g Bi in the total (n,γ) cross-section of 209 Bi according to the report [8] is equal to α 210g = 0.72. Here we present the results of depression of 210 Po production in the ADS reactor with fuel elements containing burnable absorber 10 B 4 C or zirconium hydride. Calculations were performed using the MCNP-4b code for heterogeneous model of the reactor with detailed description of fuel assemblies and the spallation neutron production target. The cross-section of radiative capture (n,γ) on 209 Bi used in MCNP-4b is shown in Figure 3. In order to estimate the amount of produced 210 Po we use the value α 210g = 0.72 from the report [8]. The reaction rate (n,γ) on 209 Bi was calculated for different parts of the reactor and is 1.5 times lower for the core with B 4 C, and 3.3 times lower for the core with H 2 Zr compared to the reference core. The amount of 210 Po produced in Pb-Bi eutectic in the reference scheme is equal to 3.6 kg/FPY. 6. Hybrid core with reference FA and FA containing zirconium hydride zones A hybrid core contains two zones with reference fuel assemblies and a small fraction of fuel assemblies with zirconium hydride. We will consider three schemes of arrangement of fuel assemblies in the reactor core: • (C1) in the first scheme the inner fuel zone (3-5 rings of hexagons in the core) contains reference FA and the outer zone (6-7 rings of hexagons) contains fuel elements with HZr cladding (see Figure 2). • (C2) fuel assemblies with HZr are arranged in 7-8 rings of hexagons so that a thick layer of Pb-Bi eutectics is located between the inner fuel zone and the outer fuel zone. • (C3) fuel assemblies with HZr layer are arranged in a scattered order in the core containing reference fuel assemblies. In all above schemes the number of fuel assemblies containing HZr is equal to 48 and their fraction is equal to 40% from the total number of fuel assemblies in the reactor core. In Table 3 main parameters for the hybrid cores are presented. For comparison the parameters of the reference core and of the core containing FA with HZr are also shown. 813
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Nuclear Development ACTINIDE AND FI
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FOREWORD The objective of the OECD/
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TABLE OF CONTENTS Foreword ........
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EXECUTIVE SUMMARY More than 160 par
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identified. In the fuel area, labor
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17:20-19:05 Session III: Partitioni
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Poster sessions Poster session: Par
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WELCOME ADDRESS Lucila Izquierdo Ge
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WELCOME ADDRESS Michel Hugon Co-ord
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WELCOME ADDRESS Philippe Savelli De
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developments. This will surely beco
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use of FBRs for transmutation toget
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view, i.e. better use of uranium an
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W. Forsberg proposes to reduce the
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1. From the open fuel cycle to the
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Figures 2 and 3 show the radiotoxic
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Denoting the transuranic (TRU) or m
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or, in terms of the fuel burn-up an
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quantities of LWR-MOX and FR-MOX wi
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view of the historic development, t
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Table 5. Assumptions for transmutat
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separating troublesome fission prod
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REFERENCES [1] L.H. Baetslé, Ch. D
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SESSION III Partitioning Chairs: J.
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OVERVIEW OF THE HYDROMETALLURGICAL
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2.1.3 Consequences Owing to the fac
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The extraction and separation mecha
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extractant was observed. As a conse
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2.3.2 Examples of strategies and
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3. Conclusions and perspectives 3.1
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SESSION IV Basic Physics, Materials
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TRANSMUTATION: A DECADE OF REVIVAL
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2.1 The IFR concept and the homogen
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2.3 Dedicated systems Making again
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compound “macro-dispersed” in M
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Figure 3. Sketch of ADS, liquid met
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3.3.2.1 The MEGAPIE project [40] ME
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3.3.2.2 The MUSE experiments The MU
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Figure 8. Comparison of the neutron
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Figure 9. Scenarios at equilibrium
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goals in this field. Since once-thr
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• The use of Thorium in PWRs alwa
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• Understanding of the role of AD
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[17] Y. Arai, T. Ogawa, Research on
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SESSION V Transmutation Systems and
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1. Introduction The term ADS compre
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• Safety should be “designed in
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3. Minor actinide and/or transurani
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Table 2. Values of Dj (neutron cons
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Table 4. Delayed neutron fraction I
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Figure 4. η (Neutrons released per
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Table 5. ADS Distinguishing feature
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While a favourable ADS safety featu
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Optimised mixes of MA and Pu can be
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Moreover, the fuel is where neutron
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REFERENCES [1] L. Van den Durpel et
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[19] D.C. Wade and E. Fujita, Trend
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POSTER SESSION Basic Physics: Nucle
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To conclude, this poster session in
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Five other papers related to ADS co
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SESSION I OVERVIEW OF NATIONAL AND
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1. Current activities for radioacti
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3.2 Results to date and analyses of
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3.2.5.2 JNC JNC is considering the
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4.6 Short-term increase in radiatio
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Annex 1 R&D scheme for partitioning
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Annex 3 Members of the Advisory Com
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plutonium can be recycled in pressu
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choices and the implementation of m
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1. Introduction Since the 5th Infor
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strata” approach which would invo
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IAEA ACTIVITIES IN THE AREA OF EMER
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actually started to do so) because
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establishment of an international R
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The accelerator driven transmutatio
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substantiate this recommendation, s
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current, advanced and innovative nu
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ACCELERATOR DRIVEN SUB-CRITICAL SYS
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demonstration of feasibility of a E
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An extended “skeleton” for ADS
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• Fertile support (uranium) is no
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7. Conclusions The TWG under the ch
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1. Introduction The priorities for
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In the EURATOM Fourth Framework Pro
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Table 2. Cluster on transmutation-t
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6. Community research for the perio
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REFERENCES [1] “Council Decision
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1. Introduction Back in 1989, the O
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would need the continuation of tech
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individual isotopes as a function o
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Therefore, while there is continuin
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[9] OECD/NEA, Overview of Physics A
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RECENT TOPICS IN R&D FOR THE OMEGA
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Figure 1. Partitioning and transmut
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The present 4-GPP necessitates a pr
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5. Concluding remarks In 1999, the
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REFERENCES [1] T. Mukaiyama, T. Tak
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1. Introduction CIEMAT is actively
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adiotoxicity to be managed could al
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Figure 3. Mass composition of the d
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Figure 6. Fuel cycle assumed in the
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the 4 batches scheme, allowing to a
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Figure 11. Transmutation efficiency
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1. Introduction Spent fuels of mode
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Figure 3. A change in radiotoxicity
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These dependencies are shown on Fig
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When increasing the moderator fract
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Even greater power increases are ob
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The effect of a moderator volume fr
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Table 11. Different isotopes contri
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Thus the transmutation of such FPs
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ASSESSMENT OF NUCLEAR POWER SCENARI
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elease probabilities. The time dist
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Table 2. Annual heavy nuclide contr
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Figure 3. Reduction of potential ra
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DISPOSAL OF PARTITIONING-TRANSMUTAT
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Figure 2. Decay heat from SNF 2000
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Figure 3. Shorter-lived HHR reposit
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4. Management of low-heat, long-liv
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isotope from other caesium isotopes
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THE AMSTER CONCEPT J. Vergnes 1 , D
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Figure 1. Layout diagram of the mol
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Table 1. Definition of configuratio
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We therefore adopted a partial purg
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conceivable. Thus by increasing the
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6. R&D needed to validate the AMSTE
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SESSION III PARTITIONING J.P. Glatz
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PARTITIONING-SEPARATION OF METAL IO
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The terpyridyl reagent (ligand L 1
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Figure 2. The synthesis of ADTPTZ a
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2.4 Implications for partitioning T
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SEPARATION OF MINOR ACTINIDES FROM
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installed in a hot cell. The feed w
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the concentrations of U, Pu and Np
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Table 2 shows the recovery in the r
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PARTITIONING ANIONIC AGENTS BASED O
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which of these, the Co 3+ , Fe 3+ a
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This dianionic species must be extr
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Figure 6 Ph 2 P acetone PPh 2 H2 O
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Figure 9 H 3 C RO(CH 2 )n CH 3 (CH
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[7] J. Rais and P. Selucky, Nucleon
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PYROCHEMICAL PROCESSING OF IRRADIAT
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The metallic cadmium product of the
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Figure 2. Schematic flow-sheet for
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R&D OF PYROCHEMICAL PARTITIONING IN
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(first of all pumps) for fluoride m
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4. Research on material and equipme
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REFERENCES [1] Uhlir J., Pyrochemic
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1. Introduction The increasing inte
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Figure 2. Stainless steel box with
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Figure 4. U deposit on solid cathod
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Figure 7. Schematic flow of the cou
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actinide elements from spent (metal
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DEVELOPMENT OF PLUTONIUM RECOVERY P
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uranium dendrite and that uranium c
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Table 1. Conditions and results of
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Cathode potential went down to -1.6
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Figure 6. Change of LCC potential i
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Figure 9. Relation between Pu conce
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consideration described in the prec
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[13] Y. Arai, S. Fukushima, K. Shio
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SESSION IV BASIC PHYSICS, MATERIALS
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1. Introduction The reduction of th
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agrees ours within limits of errors
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Figure 1. Thermal neutron capture c
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[18] A.P. Baerg, R.M. Bartholomew,
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1. Introduction Nowadays it is well
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In order to describe the inter-nucl
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kind of measurements allow to chara
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Figure 6. Two-dimensional cluster p
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Figure 8. Excitation functions for
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REFERENCES [1] D. Ridikas, thesis,
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1. Introduction Since 1991, the Com
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Experimental reactivity control tec
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Table 2. Neutron intensities Target
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experimental channels (horizontal a
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376
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Table 3. Planned experimental progr
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1. Introduction and benchmark speci
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neutrons. Since the neutron flux is
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Figure 2. Microscopic capture cross
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Figure 4. k eff variation in the st
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2.4 Neutron flux distribution One r
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etween the highest and the lowest v
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The isotope specific β eff values
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SESSION IV BASIC PHYSICS, MATERIALS
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1. Introduction Due to its excellen
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Figure 2. Tests scheme 0 340 h. 1 0
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Figure 4. Auger depth profile conce
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Figure 8. Auger depth profile conce
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deposited at the cold zone, and the
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inner layer grows inward from the o
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[8] V.M. Fedirko, O.I. Eliseeva, V.
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1. Introduction One of the main par
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3. Tantalum target irradiation The
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At 10-MeV neutron irradiation, radi
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1. Introduction HYPER (HYbrid Power
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this study, we used an orthogonal c
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Figure 5. Temperature distribution
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Figure 7. Thermal stress distributi
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FUEL/TARGET CONCEPTS FOR TRANSMUTAT
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(U 0.55 Pu 0.4 Np 0.05 )O 2 fuels w
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Figure 3. Left: Ceramograph of a (Z
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Figure 6. Left: ceramograph of a(Zr
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AMERICIUM TARGETS IN FAST REACTORS
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The reference case for all comparis
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It should be underlined that this c
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Cases Table 3. Heterogeneous recycl
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• A later step could be to add Cm
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RESEARCH ON NITRIDE FUEL AND PYROCH
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temperature for (Cm,Pu)N followed t
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Figure 1. Temperature dependence of
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The difference of two fuel pins exi
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In addition to the voltammetric stu
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2 wt% of Pu at 773 K. For the momen
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[13] M. Akabori, M. Takano, A. Itoh
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1. Introduction For the management
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The scientific feasibility of pluto
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Another option using a basis of sta
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6.2.1 Inert matrices 6.2.1.1 MgAl 2
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eached respectively 38.5% and 70% F
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Figure 4. Experiments for MA transm
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Figure 5a. Ecrix B rig Figure 5b. E
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A CEA/Minatom work programme is und
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9.3 Programme for dedicated fuels F
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[14] R.J.M. Konings et al., The EFT
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1. Introduction An accelerator driv
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corresponding Pb-Bi velocity is 1.1
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the fission product target. The rod
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fuel rods are at the TRU assembly t
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SESSION V TRANSMUTATION SYSTEMS AND
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1. Introduction Since the 50s, nitr
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A three dimensional model of a sub-
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Figure 4. Change in k-eigenvalue fo
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[4] Y. Arai et al., Experimental Re
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Nomenclature ADS: ATW: GT-MHR: LOF:
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Regarding switching off the beam, o
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Figure 3. Beam blocking 10 min (200
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Figure 7. A possible scenario for n
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[15] Greenspan E. et al., The Encap
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1. Introduction In the EADF design
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Equation (6) can be improved by con
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where L is obtained by a summation
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Figure 1. The natural convection im
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Figure 4 shows the temperature tren
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[12] P.H. Wakker, Thermal Hydraulic
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1. Introduction Research and develo
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Table 2. Core design parameters for
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2.2 Representation of MA transmutat
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Figure 1(b) shows the cases for the
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It is found that the higher MA tran
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REFERENCES [1] T. Ikegami, H. Hayas
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1. Introduction The management of t
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Table 1. Core performance of MA and
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Figure 3. Nuclear electricity capac
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Table 3. Experimental items at PEF
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REFERENCES [1] Takano H., Akie H.,
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1. Introduction and background The
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neutron source, the reactor can mai
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atoms. For fuel region Rf = 2.5 cm,
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Figure 3. Neutron flux spectra for
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A possible way to maintain the k ef
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higher than 99% of 239 Pu, and high
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TRANSMUTATION OF NUCLEAR WASTES WIT
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Figure 1. PBT conceptual view Table
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very tight holders for fission frag
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5. Cooling system A preliminary des
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spectral densities [10,11] and can
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MYRRHA, A MULTI-PURPOSE ADS FOR R&D
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hexagonal assemblies of 122 mm plat
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to achieve the requested performanc
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3 MYRRHA associated R&D programme F
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collaboration with Forschungszentru
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• Industrial partners, in particu
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1. Introduction The transmutation o
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Existing accelerators have been des
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suggested to look for an innovative
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Table 1. Main lead-bismuth eutectic
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4.3 The core The basic fuel sub-ass
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Figure 1. Experimental accelerator
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HELIUM-COOLED REACTOR TECHNOLOGIES
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of its potential use in nuclear wea
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Figure 2. Neutron flux distribution
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atio. Given this rate of destructio
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Figure 5. Irradiated TRISO particle
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in ceramic-coated microspheres of t
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(LOCA) event. The effect on this fe
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Figure 13. Elevation AD-FMHR The fa
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Deep burn-up of 239 Pu and fissiona
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POSTER SESSION PARTITIONING M.J. Hu
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1. Introduction The study of the be
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Plutonium was simulated with the no
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The influence of uranium and pluton
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The influence of uranium and pluton
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REFERENCES [1] I.I. Nazarenko, A.M.
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1. Introduction The long-term radio
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Ce Ce 3+ Cl - Cl 2 The voltammogram
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Figure 3. Chronopotentiograms for t
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Figure 4. Potentiometric titrations
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Experimental solubilization tests w
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[13] H. Flood T. Förland and K. Mo
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1. Introduction The separation of l
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Figure 4. Synthesis of amides 11-15
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1. Introduction Over the recent yea
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2.3.2 Set-up We set up a single HFM
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lower flow rates, Am(III) would be
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THE POTENTIAL OF NANO- AND MICROPAR
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efficiently and stable. This can be
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Figure 1a. Zetapotential of NTA-mod
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Scheme 7. Magnetic silica particles
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[13] L.H. Delmau, N. Simon, M.J. Sc
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1. Introduction 137 90 Extraction p
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Figure 3. Schematic drawing of the
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(24), 8-PhPO(OH)-O-COSAN (25), and
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REFERENCES [1] Kyrš M., +H PiQHN S
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1. Introduction A heavy-water CANDU
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These data show that fuel lifetime
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RECENT PROGRESSES ON PARTITIONING S
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hot tests (See Table2) was enough f
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trace amount of Am and Eu. The HBTM
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6. Conclusion Declassification of t
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POSTER SESSION BASIC PHYSICS: NUCLE
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1. Introduction Among the large num
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The simulation of the spallation pr
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Table 1. Parameters of the two coll
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Figure 4. Radial distribution of th
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6. The neutron escape line The comm
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Figure 7. Neutron background at the
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RECENT CAPTURE CROSS-SECTIONS VALID
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Figure 1. The GENEPI accelerator an
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2.3.3 Neutron flux measurements •
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Figure 6. Time spectrum of 3 He gas
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4. Analysis 4.1 Background subtract
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Figure 11. ENDF/B-VI, JEF2.2 and JE
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DOUBLE DIFFERENTIAL CROSS-SECTION F
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3. Conclusion Double differential c
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Figure 3. Preliminary results of do
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MEASUREMENTS OF PARTICULE EMISSION
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2. Experimental set-up The experime
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4. Results Figure 3 presents neutro
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1. Introduction Intermediate-energy
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Table 1. Relative neutron-induced c
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elow about 70 MeV [24] , where σ n
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Since for sub-actinides Γ f /Γ n
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[10] V.P. Eismont, A.V. Prokofiev,
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NUCLEON-INDUCED FISSION CROSS-SECTI
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Figure 1. Scheme of the new code Z
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Figure 3. Neutron-induced fission c
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REFERENCES [1] J. Raynal, Proceedin
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1. Introduction During the past few
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(same surface and 0.5 mm thickness)
Page 746 and 747:
Figure 2. Dependence of the total a
Page 748 and 749:
Figure 3. Neutron radiative capture
Page 750 and 751:
[8] MCNP, A General Monte Carlo Cod
Page 752 and 753:
1. Introduction New reactors using
Page 754 and 755:
Figure 1. Excited states of 209 Bi
Page 756 and 757:
Figure 3. The fission probability o
Page 759 and 760:
MEASUREMENT OF DOUBLE DIFFERENTIAL
Page 761 and 762: Figure 1. Global view of the experi
Page 763 and 764: To get the proton (deuteron) energy
Page 765 and 766: 3.1 Corrections Several corrections
Page 767 and 768: Figure 11. Active target fraction (
Page 769 and 770: d 2 σ Figure 14. Proton for n + Pb
Page 771 and 772: HIGH AND INTERMEDIATE ENERGY NUCLEA
Page 773 and 774: eactions, since the pre-equilibrium
Page 775 and 776: calculate the very short-lived radi
Page 777 and 778: cross-sections; the secondary react
Page 779 and 780: All possible nuclear reactions will
Page 781 and 782: A STUDY ON BURNABLE ABSORBER FOR A
Page 783 and 784: 2. Burnable absorber for HYPER 2.1
Page 785 and 786: Table 2. One-group effective cross-
Page 787 and 788: of the core, is directly determined
Page 789 and 790: Figure 4. Required proton beam curr
Page 791 and 792: Figure 8. 10 B depletion in HYPER-H
Page 793: POSTER SESSION TRANSMUTATION SYSTEM
Page 796 and 797: 1. Introduction In the framework of
Page 798 and 799: Φ >1 MeV = 1.0 10 13 to 1.0 x 10 1
Page 800 and 801: 3. Irradiation targets and irradiat
Page 802 and 803: e transmuted in BR2 hence remain va
Page 804 and 805: Table 6. Atom percent concentration
Page 806 and 807: advantage, with respect to FRs, of
Page 809 and 810: ENHANCEMENT OF ACTINIDE INCINERATIO
Page 811: Here Σ fC , ( E) are the fission a
Page 815 and 816: Table 3.Neutronics parameters of hy
Page 817 and 818: Figure 3. Neutron spectra averaged
Page 819 and 820: containing FA with B 4 C cladding i
Page 821: REFERENCES [1] ANSALDO Technical Re
Page 824 and 825: 1. Introduction At present, there a
Page 826 and 827: target means a change in k and the
Page 828 and 829: Following the normal procedure for
Page 830 and 831: Acknowledgements This study has bee
Page 832 and 833: 1. ADS description A conceptual des
Page 834 and 835: Substitution of (9) into (8), and u
Page 836 and 837: With the coupling LAHET + MCNP-DSP,
Page 838 and 839: Figure 3. Comparison for 1 and 5 pu
Page 841 and 842: MOLTEN SALTS AS POSSIBLE FUEL FLUID
Page 843 and 844: 2. The fuel salt for MSB concept Ma
Page 845 and 846: and minor actinides must be removed
Page 847 and 848: 4. Container material studies 4.1 F
Page 849 and 850: management. The major developments
Page 851: REFERENCES [1] H.J. MacPherson, Dev
Page 854 and 855: 1. Introduction The Energy Amplifie
Page 856 and 857: Table 1. Main parameters of the EAD
Page 858 and 859: Table 5. Neutron balance in the who
Page 860 and 861: Table 7. Neutron flux distributions
Page 862 and 863:
Table 8. Displacement rates DPA/yea
Page 865 and 866:
DEEP UNDERGROUND TRANSMUTOR (PASSIV
Page 867 and 868:
passive state. By operating at a hi
Page 869 and 870:
I have proposed using an accelerato
Page 871 and 872:
Figure 1. Layout of deep undergroun
Page 873 and 874:
RADIATION CHARACTERISTICS OF PWR MO
Page 875 and 876:
Table 1. Radiotoxicity of actinides
Page 877 and 878:
RADIATION CHARACTERISTICS OF URANIU
Page 879 and 880:
Table 1. Radiotoxicity of actinides
Page 881 and 882:
INTERNATIONAL CO-OPERATION ON CREAT
Page 883 and 884:
an international base to combine ef
Page 885:
• Second topic: interaction of pr
Page 888 and 889:
1. Introduction The role of acceler
Page 890 and 891:
MEPI within the framework of Projec
Page 893 and 894:
NEW ORIGINAL IDEAS ON ACCELERATOR D
Page 895 and 896:
During conceptual investigations of
Page 897 and 898:
delay, interface and computer. The
Page 899 and 900:
2. Channel-vessel design of ADS bla
Page 901 and 902:
Table 1. Characteristics of the ful
Page 903:
[14] Karavaev G.N., Kiselev G.V., M
Page 906 and 907:
1. Introduction The problem of nucl
Page 908 and 909:
Table 3. Radiotoxicity in americium
Page 910 and 911:
Table 5. Characteristics of station
Page 912 and 913:
1. Introduction The atomic power en
Page 914 and 915:
of lead-bismuth target are given in
Page 917 and 918:
CRITICAL AND SUB-CRITICAL GT-MHRs F
Page 919 and 920:
Table 1. Basic GT-MHR reactor param
Page 921 and 922:
Figure 2. Typical change of the ave
Page 923 and 924:
Scenario S4. This case is actually
Page 925 and 926:
Figure 3. A change in radiotoxicity
Page 927:
[13] P. Goberis, Modelling of Innov
Page 930 and 931:
1. Introduction The Nuclear Enginee
Page 932 and 933:
Some simplifications have been made
Page 934 and 935:
Figure 3. Velocity vectors Some of
Page 936 and 937:
Figure 6. Temperature evolution at
Page 938 and 939:
• Two main reasons can explain th
Page 940 and 941:
1. Introduction Actually, we notice
Page 942 and 943:
This problem can be solved by using
Page 944 and 945:
The evaluations obtained in [2] hav
Page 946 and 947:
REFERENCES [1] Management and Dispo
Page 948 and 949:
1. Background Radiation background
Page 950 and 951:
the long-term hazard of spent fuel,
Page 952 and 953:
In a transmutation fuel cycle inclu
Page 954 and 955:
Figure 4. Potential biological haza
Page 956 and 957:
cooling prior to SF reprocessing an
Page 958:
REFERENCES [1] White Book of Nuclea
Page 961 and 962:
ORDER FORM OECD Nuclear Energy Agen
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