ORNL-2106 - the Molten Salt Energy Technologies Web Site

ORNL-2106 - the Molten Salt Energy Technologies Web Site ORNL-2106 - the Molten Salt Energy Technologies Web Site

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ANP PROJECT PROGRESS REPORT a 2.32-Mev alpha particle is given off and that in the remaining 7% a 2.8-Mev alpha particle is given off.ll The heating from beta decay resulting from neutron captures in copper was calculated, and it was found to be negligible compared with the a Ipha-part ic le heating. The gamma-ray heating resulting from the emission of decay gamma radiation in the heat exchanger was calculated on the basis of slab geometry by using Eq. 6 for each energy group. The spectrum of gamma rays was divided into the seven energy groups given in ref. 3, with average energies of 0.5, 1, 2, 4, 6, 8, and 10 MeV. The buildup factor for the heat exchanger was used for each energy group. The total heating at various points was calculated by summing over the contributions of each energy group. The source strength of the gamma rays resulting from inelastic neutron scattering in the beryllium reflector was also calculated. These sources are appreciable only in the first 9 cm of beryllium. However, their contributions to the heating in the regions around the heat exchanger are small compared with those of the beryllium capture gamma-ray sources. The reason for this is that the gamma rays from inelastic scattering were taken to be I-Mev gamma rays, which are at- tenuated much more strongly by the beryllium than are the bMev capture gamma rays. In addition the total source strength of the gamma rays from inelastic neutron scattering is much smaller than that of the capture gamma rays because of the volumes of beryllium involved in each. The source strength of the capture gamma rays resulting from delayed neutron captures was calculated by assuming that 50% of the delayed neutrons were given off in the heat exchanger and that all these neutrons were captured in the neighborhood of the heat exchanger. By assuming that an &Mev gamma ray was given off for each capture, the average source strength per unit volume was found to be small as compared with the other sources in this region. The capture gamma-ray sources in the copper were calculated in the same general way that the alpha-particle heating in the copper was calcu- lated, with the source converted to a surface source of gamma rays. In itself this is not an insignificant source, but the heating resulting from this source would be only about 2% of the total from all the sources considered here. 34 The gamma.rays resulting from inelastic neutron scattering in the core shells were calculated by using the Curtiss-Wright multigroup fluxes5 and an inelastic microscopic cross section of 1.5 barns (ref. 13) for the constituents of Inconel. It was assumed thaf a 2-Mev gamma ray was given off for each inelastic collision. The results gave a source strength of about 10% of that resulting from the capture gamma rays in these shells. As has already been remarked, the capture gamma rays in the island core shell were neglected because of the shielding properties of the fuel. Where it has not been stated otherwise, the dimensions used in these calculations were those from ref. 1 for the equatorial plane of the reactor. RADIATION HEATING IN VARIOUS REGIONS OFTHENORTHHEAD H. W. Bertini D. L. Platus14 Calculations of the radiation heating to be ex cted in various regions in the north head of the ART were undertaken in order to supply pt numbers from which thermal-stress calculations could be made. Because of the complexity and the time that would be involved in calculating accurately the heating in all the regions of the north head, it was decided to make preliminary estimates of the deposition rates. More accurate values calculated for other regions of the reactor were used as guides. In all cases the tendency was to overestimate the heating. These estimates can be used to identify the thermal-stress problems, and where the calculated thermal stresses are marginal, the heating will be recalculated, Calculations were made of the heat-deposition rate in a slab of lnconel bounded on one side by an infinite fuel region containing the sources of radiation. This heat-generation rate was used in all regions in the north head which are bounded by finite fuel volumes, The heat-deposition rates in a slab of lnconel bounded on one side by slabs of sodium of various thicknesses were calculated, and the results were extrapolated and interpolated to obtain the heat- generation rates in the lnconel regions of the north 13H. Le Taylor, 0. Lonsio, and T. W. Bonner, Pkys. Rev. 100, 174 (1955). assignment from USAF. LI 8 e- c . . t c 9

head which are bounded by various thicknesses of sodium. Fairly accurate calculations have been made of the heat-deposition rates in the lnconel filler plates below the island and in the vicinity of the fuel-to-NaK heat exchanger on the equatorial plane of the reactor. These results were used as a guide in estimating the heating in some north-head regions, and new values were obtained by compensating (by simple exponential attenu- ation) for decreased beryllium thicknesses, penetrations through additional fuel layers, increased thermal-neutron leakage currents into the north head, etc. A neutron current of 7 x 10’3 neutrons/cm2*sec was assumed to be escaping uniformly from the upper portion of the core,’5 and it was assumed that 1 Mw of fission power was being generated in the fuel regions of the north head by neutrons escaping into this region. The latter increased the gamma rays in the fuel by about 30%. The sources of gamma radiation considered were those from the sodium and fuel in the north head, the heat exchangers, boron, the fuel in the core, core shells, beryllium, and lnconel shell capture gammas. The sources of beta particles considered were those from the gases in the fuel-expansion tank, and the sources of alpha particles were taken to be those from boron captures. The average values of heat generation obtained in these calculations are presented in Table 1.2.2. The configuration of the north head is shown in Fig. 1.1.5 of Chap. 1.1 of this report. BETA- AND GAMMA-RAY ACTIVITY IN THE FUELEXPANSIONCHAMBERANDTHE OFF-GAS SYSTEM R. B. Stevenson16 The power-source distribution of the acti the gases in the space above the fuel in the fuel expansion chamber and in the off-gas line has ’’AI M.- Parry, L, private communication to H. W. Bertini. 160n assignment f 17J. J. Newgard, Fission Product Activity and Dec Heat Distribution in the Circulating Fuel Reactor with Fission Gas Stripping, TIM-205 (Sept. 28, 1955). A = volume flow rate of fuel through purging pumps = total volume of fuel PERIOD ENDING JUNE 10, 1956 been determined. The results obtained are to be used in the calculation of the radiation heating and the thermal stresses in this region of the reactor. The radioactive constituents of the gas in this space are the gaseous fission products, xenon and krypton, and their daughter products. There is also a possibility that some volatile fission- product fluorides will be formed in the fuel and will escape into this area. However, it has been shown l 7 that if all the fission-product fluorides entered this space, they would add very little activity to that already caused by the gaseous fission products and their daughters. Thus, their effect has been neglected here. Also, there is some question as to whether the daughter products of the fission gases will actually be carried downstream by the off-gas system or whether they will be deposited on the enclosing walls as they are formed. In order to get a conservative estimate of the power-source distribution, if was decided to treat the daughter products of xenon and krypton as gases (except insofar as their purging from the fuel into the fuel expansion chamber is concerned). The equilibrium amount of the gaseous fission products in the fuel expansion chamber is given by (approximate I y) Yi’p Ni = (Ai + A,) (Ai + AS) where Ni is the total number of atoms of type i in the gas volume per fission per second, yi is the saturation fission yield of the ith nuclide, A, is the “purging” constant, As is the “sweeping” constant, and Ai is the decay constant of the ith nuclide. The “purging” constant is determined by the volume flow rate of the fuel through the purging pumps and the total volume of fuel. This constant determines the amount of the gaseous fission products which are purged from the fuel into the expansion chamber. The “sweeping” constant is determined by the flow rate of helium through the expansion chamber and the volume of the gas space. This constant determines the dwell time of the radioactive nuclides in the gas space and thus the number of disintegrations they suffer there. The “purging” and “sweeping” Constants are given by volume flow rate of helium through expansion chamber volume of gas space , 35

head which are bounded by various thicknesses of<br />

sodium.<br />

Fairly accurate calculations have been made of<br />

<strong>the</strong> heat-deposition rates in <strong>the</strong> lnconel filler<br />

plates below <strong>the</strong> island and in <strong>the</strong> vicinity of <strong>the</strong><br />

fuel-to-NaK heat exchanger on <strong>the</strong> equatorial<br />

plane of <strong>the</strong> reactor. These results were used<br />

as a guide in estimating <strong>the</strong> heating in some<br />

north-head regions, and new values were obtained<br />

by compensating (by simple exponential attenu-<br />

ation) for decreased beryllium thicknesses,<br />

penetrations through additional fuel layers,<br />

increased <strong>the</strong>rmal-neutron leakage currents into<br />

<strong>the</strong> north head, etc.<br />

A neutron current of 7 x 10’3 neutrons/cm2*sec<br />

was assumed to be escaping uniformly from <strong>the</strong><br />

upper portion of <strong>the</strong> core,’5 and it was assumed<br />

that 1 Mw of fission power was being generated in<br />

<strong>the</strong> fuel regions of <strong>the</strong> north head by neutrons<br />

escaping into this region. The latter increased<br />

<strong>the</strong> gamma rays in <strong>the</strong> fuel by about 30%.<br />

The sources of gamma radiation considered<br />

were those from <strong>the</strong> sodium and fuel in <strong>the</strong> north<br />

head, <strong>the</strong> heat exchangers, boron, <strong>the</strong> fuel in <strong>the</strong><br />

core, core shells, beryllium, and lnconel shell<br />

capture gammas. The sources of beta particles<br />

considered were those from <strong>the</strong> gases in <strong>the</strong><br />

fuel-expansion tank, and <strong>the</strong> sources of alpha<br />

particles were taken to be those from boron<br />

captures. The average values of heat generation<br />

obtained in <strong>the</strong>se calculations are presented in<br />

Table 1.2.2. The configuration of <strong>the</strong> north head<br />

is shown in Fig. 1.1.5 of Chap. 1.1 of this report.<br />

BETA- AND GAMMA-RAY ACTIVITY IN THE<br />

FUELEXPANSIONCHAMBERANDTHE<br />

OFF-GAS SYSTEM<br />

R. B. Stevenson16<br />

The power-source distribution of <strong>the</strong> acti<br />

<strong>the</strong> gases in <strong>the</strong> space above <strong>the</strong> fuel in <strong>the</strong> fuel<br />

expansion chamber and in <strong>the</strong> off-gas line has<br />

’’AI M.- Parry, L, private communication to<br />

H. W. Bertini.<br />

160n assignment f<br />

17J. J. Newgard, Fission Product Activity and Dec<br />

Heat Distribution in <strong>the</strong> Circulating Fuel Reactor with<br />

Fission Gas Stripping, TIM-205 (Sept. 28, 1955).<br />

A =<br />

volume flow rate of fuel through purging pumps<br />

= total volume of fuel<br />

PERIOD ENDING JUNE 10, 1956<br />

been determined. The results obtained are to be<br />

used in <strong>the</strong> calculation of <strong>the</strong> radiation heating<br />

and <strong>the</strong> <strong>the</strong>rmal stresses in this region of <strong>the</strong><br />

reactor.<br />

The radioactive constituents of <strong>the</strong> gas in this<br />

space are <strong>the</strong> gaseous fission products, xenon<br />

and krypton, and <strong>the</strong>ir daughter products. There<br />

is also a possibility that some volatile fission-<br />

product fluorides will be formed in <strong>the</strong> fuel and<br />

will escape into this area. However, it has been<br />

shown l 7 that if all <strong>the</strong> fission-product fluorides<br />

entered this space, <strong>the</strong>y would add very little<br />

activity to that already caused by <strong>the</strong> gaseous<br />

fission products and <strong>the</strong>ir daughters. Thus, <strong>the</strong>ir<br />

effect has been neglected here. Also, <strong>the</strong>re is<br />

some question as to whe<strong>the</strong>r <strong>the</strong> daughter products<br />

of <strong>the</strong> fission gases will actually be carried<br />

downstream by <strong>the</strong> off-gas system or whe<strong>the</strong>r <strong>the</strong>y<br />

will be deposited on <strong>the</strong> enclosing walls as <strong>the</strong>y<br />

are formed. In order to get a conservative estimate<br />

of <strong>the</strong> power-source distribution, if was decided<br />

to treat <strong>the</strong> daughter products of xenon and krypton<br />

as gases (except insofar as <strong>the</strong>ir purging from <strong>the</strong><br />

fuel into <strong>the</strong> fuel expansion chamber is concerned).<br />

The equilibrium amount of <strong>the</strong> gaseous fission<br />

products in <strong>the</strong> fuel expansion chamber is given by<br />

(approximate I y)<br />

Yi’p<br />

Ni =<br />

(Ai + A,) (Ai + AS)<br />

where Ni is <strong>the</strong> total number of atoms of type i in<br />

<strong>the</strong> gas volume per fission per second, yi is <strong>the</strong><br />

saturation fission yield of <strong>the</strong> ith nuclide, A, is<br />

<strong>the</strong> “purging” constant, As is <strong>the</strong> “sweeping”<br />

constant, and Ai is <strong>the</strong> decay constant of <strong>the</strong><br />

ith nuclide. The “purging” constant is determined<br />

by <strong>the</strong> volume flow rate of <strong>the</strong> fuel through <strong>the</strong><br />

purging pumps and <strong>the</strong> total volume of fuel. This<br />

constant determines <strong>the</strong> amount of <strong>the</strong> gaseous<br />

fission products which are purged from <strong>the</strong> fuel<br />

into <strong>the</strong> expansion chamber. The “sweeping”<br />

constant is determined by <strong>the</strong> flow rate of helium<br />

through <strong>the</strong> expansion chamber and <strong>the</strong> volume of<br />

<strong>the</strong> gas space. This constant determines <strong>the</strong><br />

dwell time of <strong>the</strong> radioactive nuclides in <strong>the</strong> gas<br />

space and thus <strong>the</strong> number of disintegrations <strong>the</strong>y<br />

suffer <strong>the</strong>re. The “purging” and “sweeping”<br />

Constants are given by<br />

volume flow rate of helium through expansion chamber<br />

volume of gas space<br />

,<br />

35

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