PROCEEDINGS OF A SYMPO - IAEA Nuclear Data Services

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30 THOM and SCHNEIDER Small Light Bulb Engine The critical fuel density and the size of a cavity reactor depend on the flow of thermalized neutrons back into the cavity. In the plasma reactor concepts previously discussed, the high-temperature propellant flow in between the fissioning plasma and the moderator-reflector region represents a significant neutron flux barrier. A concept [23] has been forwarded to largely circumvent this problem by dividing the surface area surrounding the fissioning plasma such that only a part of it is propellant flow and the other is an optically reflecting material that is highly transparent for neutrons. Part of the thermal radiation from the fuel region is directly absorbed in an array of segmented propellant flow ducts embedded in the reflecting cavity walls. Another part of the radiation is focused indirectly by reflection from such walls to such ducts. In addition, use is made of the large transparency of cold beryllium for thermal neutrons having energies below 0.006 eV. A figure of merit for the performance of reflector-moderator materials in cavity reactors is the ratio of the square root of the age of fission neutrons and the thermal neutron mean free path. For example, if this ratio is Z.25, that is, for a graphite moderator at 300°K, the critical density for 235U in a spherical cavity of 1 m radius must be greater than 10Î9 atoms/cm3. In contrast, a beryllium moderator at 100°K yields 0.47 for this ratio with a resulting critical density of 2 to 4 x 10' 7 atoms/cm3. The combined effects of a super-cooled beryllium neutron moderator and drastically reduced propellant flow areas should result in appreciably reduced critical mass for the plasma-core reactor and a low operational power. The cold beryllium has to be surrounded by a D£0 reflector to prevent neutron leakage from the system. Analysis was conducted for a spherical geometry using one-dimensional multi group neutron transport theory calculations. Seventeen neutron energy groups were employed, including five thermal groups of which two were below 0.006 eV. Scattering cross sections were taken from literature or were computed by standard methods. The neutron transport calculations were performed on a computer with the ANISN code. The system involved an argon buffer gas flow for the confinement of the fissioning plasma within the cavity and away from the walls. Results show that moderator temperature is a strong negative reactivity feedback. For example, using 233U, critical mass is slightly higher than 1 kg at a beryllium temperature of 40°K. It increases to about 2.8 kg at room temperature. The use of 235U instead of 233U results in an increase of the critical mass of about 20%. The presence of hot hydrogen ,in the discrete propellant channels does not appear to have a large effect on critical mass for the system studied. Operating power depends largely on the reflectivity of the reflecting surfaces of the cavity, which in the calculations is assumed to be of the order of 0.9. Radiation damage may, however, degrade this quality. With the previously mentioned temperature requirements for the fissioning plasma, the power is calculated to be in the range of 40 to 400 MW. The pressure may vary from 250 to 500 atm, and the weight of the system, including a pressure shell, is in the range of 16000 to 22000 kg. Applications are seen for space propulsion at specific impulse values as large as 1550 sec and for MHD power conversion. NUCLEAR DATA REQUIREMENTS The special characteristics of plasma-core reactor schemes pose a number of problems for computing criticality conditions not hitherto encountered in
<strong>IAEA</strong>-SM * 1 70/53 31 Temperature, °K F IG . 1 1 . U r a n iu m -p la s m a c o m p o s itio n at pressure o f 5 00 a tm ospheres [ 3 2 ] . reactor physics calculations. More precise knowledge of certain nuclear data that play a more important role in plasma-core reactor schemes is required. A predominant new aspect is the intimate relationship between plasma physics and reactor physics. For typical plasma-core reactor conditions at 40000°K and 500 atm, more than 70% of the particles that account for this pressure are electrons. About 15% are U IV, as can be seen from Fig.' 11. Composition calculations have thus to be included in criticality calculation and their
Page 1: PROCEEDINGS OF A SYMPO ■ i INTERN
Page 6 and 7: The follow in g States are M em ber
Page 8 and 9: N U C L E A R D A T A IN S C IE N C
Page 10 and 11: A cce le ra to r and Space Shieldin
Page 12 and 13: C r o s s -s e ctio n uncertainty e
Page 14 and 15: Evaluation of the ranges of fission
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Page 21 and 22: SYMPOSIUM KEYNOTE 7 are them selves
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SECTIONS EFFICACES DE CREATION DE D
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1 .1. Choc élastique I A E A -S M
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Section efficace de dommage Energie
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CONCLUSION IAE A - S M - 17 0 /6 5
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I A E A - S M -1 7 0 /6 5 И З TAB
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I A E A - S M -1 7 0 /6 5 117 TABLE
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IA E A -S M -1 70/65 119 TABLEAU V
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I A E A - S M -1 7 0 /6 5 121 TABLE
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IAE A -SM -1 7 0 /6 5 123 TABLEAU I
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IAE A - S M - 1 7 0 /6 5 125 REFERE
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Section II REACTOR TECHNOLOGY
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IAEA- SM-170/91 ТОЧНОСТЬ Я
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IAEA SM-170/91 131 3) Для без
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IAEA SM -170/91 133 важност
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IAEA SM -170/ 91 135 ваемых
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ТАБЛИЦА II . (продолж
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П римечания к табли
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IAEA-S M -170/91 141 ZPR-III-48 и
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I A E A - S M -1 7 0 /6 9 ROLES RES
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I A E A -S M - 1 7 0 /6 9 147 de la
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I A E A - S M -1 7 0 /6 9 149 FIG.
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I A E A -S M - 1 7 0 /6 9 T A B L E
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3 .5 . A u tr e s d em an d es I A
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CROSS-SECTION UNCERTAINTY EFFECTS O
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I A E A 'S M - 1 7 0 /7 T h e c o d
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1Л n» О О О 'í 16.375 REG. A
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EL USO DE PARAMETROS NEUTRONICOS DE
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I A E A - S M -1 7 0 /2 1 6 7 E STI
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I A E A - S M -1 7 0 /1 8 ASSESSMEN
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I A E A -S M -1 7 0 /1 8 177 routin
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I A E A - S M -1 7 0 /1 8 179 TABLE
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I A E A - S M -1 7 0 /1 8 181 and
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I A E A - S M -1 7 0 /1 8 183 WIMS
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IAEA-SM-170/18 185 For the discrepa
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IAEA -S M -1 7 0 /6 7 UTILISATION D
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1. 5. Nouvel intérêt des m esures
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IA E A -SM -17 0 / 67 193 P ar aill
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Section III SAFEGUARDS
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THE ROLE OF NUCLEAR DATA IN NUCLEAR
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IA E A -S M -1 70/7 8 199 I n s t e
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IA E A -S M -1 70/78 201 s t a t e
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IA E A -S M -1 70/78 203 s p e c t
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TABLE V . DECAY ENERGY Q, H A L F-L
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IA E A -S M -1 70/7 8 209 TA B L E
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IA E A -S M -1 70/7 8 211 T a b l e
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IAEA-SM “ 17 0 /7 8 213 (1) E v e
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IA E A -S M -1 70/78 l_ 36 / G O Z
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IA E A -SM -П О /5 4 THE ROLE OF
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IAEA-SM-170/54 The assay of a fuel
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IA E A -S M -1 7 0 /5 4 221 FIG. 3.
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IA E A -S M -17 0 /5 4 223 FIG. 6.
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LAEA-SM-17 0/5 4 225 w hich time th
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IAEA-SM-170/54 227 energies b elow
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IAEA-SM-17 0/54 229 coincidence rat
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IAEA-SM-17 0/54 231 [8] MENLOVE, H.
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234 EDER and LAM M ER In a "forward
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236 EDER and LAM M ER decay during
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238 EDER and LAM M ER The ra tio o
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240 EDER and LAM M ER Step 3: The n
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242 EDER and LAM M ER FIG . 2 100 1
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244 EDER and LAM M ER gamma ray mea
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246 EDER and LAM M ER T A B L E I.
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248 EDER and LAMMER TA B L E III. F
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250 EDER and LAM M ER T A B L E III
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252 EDER and LAMMER О . О 2 5 З
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254 EDER and LAMMER T A B L E V . E
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256 EDER and LAMMER T A B L E V (co
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258 EDER and LAMMER T A B L E V I.
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260 EDER and LAMMER I n a f o r w a
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262 EDER and LAMMER 5 . 1 . 3 . D e
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264 EDER and LAMMER 5.3. Examples o
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266 EDER and LAMMER REFERENCES r d
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268 EDER and LAMMER c a r r i e d o
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270 BERENYI claims for radioactive
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T A B L E I. H A L F -L IF E O F R
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T A B L E II. Y IELD O F G A M M A
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T A B L E lib . CONTIN U ATIO N Rad
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T A B L E lid . CO N TIN U ATIO N R
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280 BERÉNYI future: it would be ve
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282 BERÉNYI [29] ARDISON, G. et MA
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Section IV LIFE SCIENCES
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LE ROLE DES DONNEES NUCLEAIRES DANS
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IA E A -S M -1 70/97 289 FIG. 1. S
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C IB L E Hg PARTICU LES iA E A -S M
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IA E A -S M -1 7 0/9 7 293 ou syst
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IAEA -SM -1 7 0 /9 7 295 Le princip
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IA E A -S M -1 70/97 nous examinero
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IA E A -S M -1 70/97 299 T A B L E
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IA E A -S M -1 70/9 7 301 capture
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lA E A -S M -1 7 0 /9 7 303 T A B L
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IA E A -S M -17 0 /9 7 305 FIG. 10.
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c o m p o s itio n du co r p s h u
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IA E A -S M -17 0 /9 7 309 (3) BÈR
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IA E A -S M -1 7 0/9 7 311 D I S C
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314 DENNIS However, these aspects a
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316 DENNIS D O S E ( K r a d s ) FI
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318 DENNIS F IG .6. An illustration
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TABLE I. SUMMARY OF I. C. R . P. RE
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322 DENNIS F IG .9. Specific energy
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324 DENNIS Similar details are requ
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326 DENNIS C l J LAURIE, J., ORR, J
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IAEA -SM-170/64 PROBLEMES POSES PAR
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IAEA-SM-170/64 331 liè r e s , dan
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IAEA-SM- П О /64 333 Le rendem en
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NUCLEAR DATA AND NEUTRON ACTIVATION
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IAEA-SM-170/3 T A B L E lia . A C T
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IAEA-SM-170/3 339 At th is stage mo
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T A B L E V b . IS O T O P IC SEN S
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IAEA-SM-ИО/З 343 TABLE VI. ELEM
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IAEA-SM-ПО/З 345 The follow ing
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IAEA-SM- ПО/З 347 TABLE IX . DET
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IAEA-SM-170/3 349 [10] SEELMANN-EGG
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352 COHEN L es radioélém en ts de
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354 COHEN TABLEAU II. CONSTANTES NU
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356 COHEN On peut pen ser que les t
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I A£ A-SM-170/92 APPLICATION OF NU
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IAE A-SM-170/92 361 The p roblem s
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4. 20N e(p ,tf)18F 5. 160 (a , 2n)1
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T A B L E I. (continu ed) 13. Oak R
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T A B L E II. SP E C IF IC A T IO N
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IAEA-SM-170/92 369 Neutrons produce
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8.3. A c c e le r a t o r p ro d u
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IAEA-SM-170/92 373 R.В.R. PERSSON:
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Chairman K.H. LIESER (Federal Repub
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378 GÓRSKI Unfortunately, the labe
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380 GÓRSKI several billions of yea
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NUCLEAR DATA REQUIRED FOR THE INTER
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IAEA-SM -170/28 385 dissipated by t
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100 10 IAEA-SM -17 0/28 387 1 5 10
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IAE A -S M -17 0/28 389 m ay not be
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Chairman G. В. YANKOV (USSR)
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394 CROUCH it was thought proper to
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396 CROUCH its uncertainty; the cha
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398 CROUCH It should also be mentio
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400 CROUCH Table I I Ac Pile Neutro
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402 CROUCH Table III (cont) Th then
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404 CROUCH Table IV Pa Pile neutron
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406 CROUCH Table V I 'Th Pile neutr
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408 CROUCH Table V (cont) 'Th Pile
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410 CROUCH 77 Ge As 347 347 Table V
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412 CROUCH Table VII (cont) 233 U T
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414 CROUCH Table VII (cont) U Therm
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420 CROUCH Table VIII (cont) U Ther
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422 CROUCH Table VIII (cont) U Ther
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424 CROUCH Table VIII (cont) 235 U
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426 CROUCH 1 2 Table VIII (cont) 23
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428 CROUCH T a b l e V I I I ( c o
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1 83 89 91 97 99 103 105 106 109 11
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432 CROUCH Table X 239 Pu Thennal n
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434 CROUCH Table X (cont) 239 Pu Th
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436 CROUCH T a b le X ( c o n t ) P
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438 C R O U C H T a b le X ( c o n
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440 C R O U C H Table XI Pu Thermal
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442 CROUCH T a b l e X I ( c o n t
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4 4 4 CRO U CH T a b l e X I ( c o
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1 83 84 89 90 91 92 93 95 97 99 103
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1 89 95 97 99 103 106 109 111 112 1
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450 C R O U C H T a b l e XVI ( c o
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452 c r o u c h Table XVI (cont) Re
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454 CROUCH T a b l e X V I ( c o n
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456 C R O U C H T a b l e X V I ( c
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458 C R O U C H m y m e m o r y goe
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460 W ALKER o b t a i n y i e l d s
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462 W ALKER a v e r a g e i s o n l
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464 W ALKER TABLE II. RELATIV E ELE
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Fission Product А Л a ± Да - b
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468 W ALKER p e r i o d . T h e t h
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470 W ALKER T A B L E IV. M A J O R
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472 W ALKER d e t e c t o r t o s o
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474 W ALKER T A B L E V . N U C L I
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476 W ALKER [1 1 ] H a w k i n g s
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478 DEVILLERS e t a l. sont sn effe
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480 DEVILLERS e t a l. . 2 3 8 U' :
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482 DEVILLERS e t a l. Les modes de
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DEVILLERS e t a l. Une table de pro
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suivantes : DEVILLERS e t a l. Les
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488 DEVILLERS e t a l. G ESTION P E
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T A B L E A U III. E N E R G I E L
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492 DEVILLERS e t a l. F I G .3 . D
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494 DEVILLERS e t a l. T A B L E A
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4 9 6 DEVILLERS e t a l. F i l e 1
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4 9 8 DEVILLERS e t a l. F i l e 1
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500 DEVILLERS et al. F i l e 1 MT =
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502 DEVILLERS et al. (2) (3 ) (4 )
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DISCUSSION OF FISSION-PRODUCT YIELD
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IAEA-SM-170/13 507 In their evaluat
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T A B L E I (continu ed) IAEA-SM-17
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IAEA-SM-170/13 511 also measured, t
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IAEA-SM-170/13 513 contribute to th
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LAEA-SM-170/13 515 The accuracy of
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IAEA-SM-170/13 517 The samples used
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LAEA-SM-170/13 519 An example o f t
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IAEA-SM-170/13 521 In the discussio
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IAEA-SM-170/13 523 data have been c
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T A B L E II (con tin u ed) fissio
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IAEA-SM-170/13 527 Apart from the f
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IAEA-SM-170/13 529 mass peak only w
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T A B L E IV (continu ed) Mass No.
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T A B L E IV (continued) Mass No. 1
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T A B L E V (continued) Mass Ko. Th
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T A B L E V (continued) Mass No. Th
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T A B L E VI (continued) Mass No. t
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T A B L E VI (continu ed) Mass No.
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IAEA-SM-170/13 543 and Scadden [9 2
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T A B L E VII (continued) Mass No.
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IAEA-SM-170/13 547 in a forthcoming
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IAEA-SM-170/13 549 [48] WAHL, A. C
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IAEA-SM-170/13 551 D I S C U S S I
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554 GRUPPELAAR 2. PRESENT SITUATION
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556 GRUPPELAAR FIG. 1. Calculated c
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558 GRUPPELAAR R E F E R E N C E S
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560 RUSTICHELLI H ow ever, by using
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562 RUSTICHELLI The en ergies of th
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T A B L E I. A B SO L U T E RANGES
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T A B L E II (continu ed) Phosphoru
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T A B L E II (continu ed) Ces i urn
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TABLE II (continued) Americî um Am
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572 RUSTICH ELLI The ra tio in air
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Section VII ACCELERATOR AND SPACE S
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I A E A - S M -17 0 /4 2 USE OF NUC
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I A E A - S M -17 0 /4 2 587 dead l
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I A E A - S M -17 0 /4 2 591 T A B
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I A E A - S M -17 0 /4 2 593 [22] V
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I A E A - S M -17 0 /3 5 NUCLEAR DA
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I A E A - S M - n O /3 5 599 o u t
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I A E A - S M -17 0 /3 5 601 r e a
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I A E A - S M -17 0 /3 5 603 F IG .
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I A E A - S M - n O /3 5 605 s y s
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TRANSPORT OF NEUTRONS INDUCED BY 8
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MAIN BEAM UNE IAEA-SM-17 0 /4 5 609
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I A E A - S M -17 0 /4 5 611 F I G
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(a) A cy lin d rica l geometry was
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I A E A - S M -17 0 /4 5 REFERENCES
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I A E A - S M -17 0 /4 5 619 is o f
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H O W T O O RD ER IAEA PUBLICATIONS
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