The first samples of this number were distributed to the public at LosCon, at the end of November 2023. Based on comments from recipients of preliminary versions, revisions were made until a final version was reached in April of 2024.
The format of this number, in which most of the space is occupied by the one long piece, The Atom in the World Energy Picture, is not intended to be typical. Hopefully future numbers will include more contributions from different hands, most of which can be expected to be brief.
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radioactive pollution, while continuing to burn coal, as Germany has.
Conder tokenswhich made up for the lack of official small change. Such tokens were produced primarily in Birmingham, and the most notable producer was the firm of Boulton and Watt — yes, that Watt. Arguably the first steam–powered manufacturing establishment in the world, Boulton and Watt achieved such technical perfection with tokens that they were ultimately chosen to supply the regal copper coinage of 1797, which rapidly drove the Conders out of circulation.
carbon intensityof different electricity sources to compare the electricity supplies of the two countries. The difference is rarely less than ten–to–one in favor of France.
unfit, and the Coney Island sideshow, see this book review.
investmentin the core. The concept of the
support ratiocan help greatly in disentangling the confusion. Converters of different designs, operated in a closed fuel cycle, require different amounts of make–up fissile material per unit of output. If we require a certain amount of energy from the overall nuclear installation, and the deficit on the converter side is to be balanced by the surplus on the breeder side, then we see two main possibilities. With breeders which produce only a modest fissile surplus per unit of energy (as is typical of designs using ceramic fuel, such as the French Superphénix), and converters with a large make–up requirement, such as the PWR, it would take more than 1 W of breeder capacity to feed each watt of converter capacity. In this case, few converters will probably be built after the breeders begin to be built on a large scale, and the surplus fissile from the breeders will mostly be dedicated to starting up further breeders. For breeders which produce more fissile, typical of metal–fuel designs such as EBR–II and its derivatives, and converters which require less, such as CANDU, each watt of breeder capacity can support considerably more than 1 W of converter capacity. This leads to a mixed system of breeders and converters.
Refrigeration, describes the absorption chiller, marketed by the Servel Corporation as
The Miracle of Ice from Heat. It is really an invention worthy of those two great lateral thinkers : a purely thermodynamic machine, composed of a sealed loop of tubing, actuated by heat, and with circulating fluids as its only moving parts. Absorption chillers today are typically either very large units, or very small ones, such as for travel trailer refrigerators. In the former case, they are typically fired by pipeline gas, sometimes by oil or even coal — whatever fuel is used by the building boiler. In the latter, they are often fitted for operation by bottle gas when the vehicle is parked, and electric heat when in motion.
power parkand
fuel cycle centerconcepts. Work relating to the Hanford site specifically is reported by Ronald K Robinson.
Atoms for Peacespeech, made before the General Assembly of the United Nations, 8 December 1953, can be heard on the Web site of the Eisenhower Presidential Library.
Big Bangmodel of cosmology (although he himself long advocated the rival
Steady–Statemodel). With his nephew Geoff, he wrote (in addition to science–fiction novels) Commonsense in Nuclear Energy (1979) and, Energy or Extinction? The Case for Nuclear Energy (1981). Not content to indicate ways that anti–nuclear campaigns in Western countries served the interests of the USSR, Sir Fred explicitly accused
Friends of the Earthof taking Soviet money. This resulted in a lawsuit and the destruction of many copies of the first printing of the book, although (with the benefit of post–1990 disclosures) it appears to have been quite true.
A Perspective on Adaptive Nuclear Energy Evolutions : Towards a World of Neutron Abundance, held 25—27 May 1981 in Heidelburg, Germany, by the International Institute for Applied Systems Analysis. Substantial coverage is given to the potential use of particle accelerators and fusion machines as neutron sources for the production of fission fuel.
Renewables face the challenge. This is separate from the regular column reporting Parliamentary debates on atomic energy and allied topics.
Year | |||||||||||||||||||||||||||
Quantity | 1 | 2 | 3 | 4 | 5 | 6 | 7 | 8 | 9 | 10 | 11 | 12 | 13 | 14 | 15 | 16 | 17 | 18 | 19 | 20 | 21 | 22 | 23 | 24 | 25 | 26 | 27 |
Assumed starting stock : spent LWR fuel equivalent to 80 000 t initial uranium.
Composition 95% U, of which, 1% 235U ; 4% fission products ; 1% total plutonium.
Enrichment tails sufficient to produce 76 000 t at 1% 235U by stripping to 0·1% 235U. | |||||||||||||||||||||||||||
FBR initial loading : 3·63 t total Pu per gigawatt electrical capacity
FBR annual Pu surplus : 184 kg (fissile)/GWe a (Tripplett et al, 2010) | |||||||||||||||||||||||||||
CANDU burn–up with uranium fuel of 1% 235U content is taken as 20 MWd/kg,
with thermal efficiency of 30%, requiring 60 833 kg/GWea of fuel.
Plutonium content of discharged fuel is taken as 0·62%, or 377 kg/GWea. (Croff and Bjerke, 1980) | |||||||||||||||||||||||||||
Pu from reprocessing of LWR fuel is dedicated to FBR cores only.
Pu surplus from FBRs is added to recovery from uranium–fueled HWRs, in that year, and the Pu requirements for HWR fuel in that year deducted. The remaining Pu is passed alongto the fabrication of FBR cores in the following year. Plutonium recovered from Pu–fueled HWRs is taken as recycled into HWR fuel, and thus does not appear in the material balance. | |||||||||||||||||||||||||||
Uranium from LWR fuel [t] | —3800— | —0— | |||||||||||||||||||||||||
U from enrichment tails [t] | —3800— | —0— | |||||||||||||||||||||||||
U to (from) stockpile [t] | 5926 | 3445 | (228) | (5670) | (3472) | —0— | |||||||||||||||||||||
Plutonium from LWR fuel [t] | —40— | —0— | |||||||||||||||||||||||||
Pu from HWR fuel [t] | 17·2 | 42·7 | 80·5 | 136 | 114 | —78·2— | —0— | ||||||||||||||||||||
Pu from FBR surplus [t] | 2·0 | 5·0 | 9·5 | 16·1 | 25·8 | 34·4 | 41·1 | 47·8 | 54·6 | 61·5 | 68·5 | 75·5 | 82·5 | 89·7 | 96·9 | 104 | 111 | 119 | 126 | 134 | 140 | 141 | 142 | 143 | 145 | 146 | 148 |
Pu passed alongto FBR cores [t] |
19·3 | 47·8 | 90·0 | 153 | 130 | 92·0 | 93·3 | 94·5 | 95·8 | 97·0 | 98·3 | 99·6 | 101 | 102 | 104 | 105 | 106 | 108 | 109 | 110 | 25·8 | 26·0 | 26·3 | 26·5 | 26·8 | 27·0 | 27·3 |
Net Pu to HWR fuel [t] | —0— | 10·1 | 20·5 | 26·0 | 31·5 | 37·1 | 42·7 | 48·3 | 54·0 | 59·8 | 65·6 | 71·5 | 77·4 | 83·4 | 89·4 | 95·5 | 101 | 113 | 115 | 116 | 117 | 118 | 119 | 120 | |||
FBR capacity constructed [GWe] | 11·0 | 16·3 | 24·2 | 35·8 | 53·0 | 46·7 | 36·3 | 36·7 | 37·0 | 37·4 | 37·7 | 38·1 | 38·4 | 38·8 | 39·2 | 39·5 | 39·9 | 40·3 | 40·6 | 41·0 | 30·4 | 7·1 | 7·2 | 7·2 | 7·3 | 7·4 | 7·4 |
Total FBR capacity [GWe] | 11·0 | 27·3 | 51·5 | 87·3 | 140 | 187 | 223 | 260 | 297 | 334 | 372 | 410 | 449 | 487 | 527 | 566 | 606 | 646 | 687 | 728 | 758 | 765 | 772 | 780 | 787 | 794 | 802 |
HWR capacity constructed [GWe] | 27·5 | 40·8 | 60·4 | 89·5 | 133 | 117 | 90·9 | 91·7 | 92·6 | 93·4 | 94·3 | 95·2 | 96·1 | 97·0 | 97·9 | 98·9 | 99·7 | 101 | 102 | 103 | 76·0 | 17·7 | 17·7 | 18·1 | 18·2 | 18·4 | 18·6 |
Total HWR capacity [GWe] | 27·5 | 68·3 | 129 | 218 | 351 | 467 | 560 | 650 | 742 | 836 | 930 | 1025 | 1121 | 1218 | 1316 | 1415 | 1515 | 1615 | 1717 | 1820 | 1896 | 1913 | 1931 | 1949 | 1967 | 1986 | 2004 |
HWR capacity fed with U [GWe] | 27·5 | 68·3 | 129 | 218 | 182 | —125— | —0— | ||||||||||||||||||||
HWR capacity fed with Pu [GWe] | —0— | 169 | 342 | 433 | 525 | 618 | 711 | 805 | 900 | 996 | 1093 | 1191 | 1290 | 1389 | 1490 | 1592 | 1695 | 1896 | 1913 | 1931 | 1949 | 1967 | 1986 | 2004 | |||
Electric Generation [GW] | 38·5 | 95·6 | 180 | 305 | 491 | 654 | 781 | 910 | 1040 | 1170 | 1302 | 1435 | 1570 | 1706 | 1843 | 1981 | 2121 | 2262 | 2404 | 2547 | 2654 | 2679 | 2704 | 2729 | 2755 | 2780 | 2806 |
To simplify calculation, a 100% annual load factor has been used.
In other words, each gigawatt of reactor capacity is taken as generating 8760 gigawatt–hours of electricity a year.
This is not possible in practice, and as a result, in any real system, the investment of fuel in reactor cores,
per gigawatt–year of generation, will be greater.
As a further simplification, only the annual fuel use of the converter reactors has been considered.
Of course, a reactor cannot be started up without a full load of fuel, and if a fuel bundle stays in the reactor
for three to five years, then a corresponding amount is required in the beginning.
This can be offset to an extent, for instance, by part–loading with plain thorium or depleted
uranium,
and by fuel shuffling, but it is a complicating effect which must be accounted for in framing a realistic model.
In this instance, it is partly represented by the uranium which is initially stockpiled
.
The construction rates shown, peaking at about 150 GW/a, may appear astonishing, far beyond anything so far achieved. The vital point is, however, that for the kind of universal electrification now being advocated, something will have to be built at this kind of rate. The products of well–established heavy industries, which can be installed on a limited number of modestly–sized sites, and do not require the wholesale reconstruction of power networks, have a strong claim to consideration. Indeed, wind and solar would require installation of a much greater (perhaps 5×) nameplate capacity to generate the same number of annual units, only to require replacing at 12—20 year intervals. Electrochemical storage systems, often promoted in conjunction with wind and solar, are even worse. Not only would they have to be installed on a scale hitherto altogether unheard–of, but they can scarcely be expected to last more than 3—5 years in heavy service. It is difficult to see how anything can be achieved with such inadequate means.
Clearly, the weak point in this calculation is the support ratio of 2·5.
If this cannot be justified, all else falls.
A quick evaluation is not promising : with the CANDU performance assumed, an input of 608 kg 235U
is offset by a production of 377 kg total plutonium.
Even assuming this Pu to be 1:1 equivalent to 235U, a deficit of at least 231 kg must be made up,
which is greater than the Pu surplus per GWea of S–PRISM in the high gain
configuration.
Adding in the residual 235U, about 46 kg, only brings us to a support ratio of unity.
Even adding in the 236U, about 89 kg,
which would correspond to 240Pu in a fully plutonium–fueled system,
does not get us to anything like the 60 kg/GWea make–up fissile assumed.
The use of thorium as fertile material helps to economize on fissile material, because the 232Th nucleus has a capture cross–section for slow neutrons more than 2·5× that of 238U. (See figure, page 6.) This makes it a more effective competitor against neutron–absorbing fission products. As metal or oxide, thorium also changes its properties more slowly under neutron bombardment than uranium does, meaning that thorium fuel bundles can be left in the reactor longer, saving on reprocessing and refabrication costs. It has been suggested that a fast breeder could be built to accept fuel bundles fabricated from plain thorium in its outer blanket, which would be discharged at a certain fissile content, and then loaded directly into a converter. Set against this is a much smaller probability of fast–neutron fission compared to 238U. The fissile species produced, 233U, has a smaller fission cross–section than either 235U or 239Pu, so that more of it is required for criticality, but its tendency to absorb a slow neutron and not fission is particularly small, making for better overall economy.
A word about the treatment of 240Pu,
produced by about a quarter of all slow–neutron absorptions in 239Pu :
although this isotope is not fissile — that is, it does not fission with neutrons of all energies,
and thus cannot sustain a chain reaction by itself — it has a much larger fast–neutron fission
cross–section, and a lower neutron–energy threshold for fast fission, than nuclei such as 238U.
For this reason, depending on reactor design, it is typically assigned an equivalent worth
, gram for gram,
in the fast reactor of about 0·3× 239Pu, taken as a reference fuel.
In a plutonium–fueled converter, 240Pu absorbs a neutron, producing 241Pu,
which has an even higher fission cross–section and neutron yield than 239Pu.
The resulting disappearance of an absorber and appearance of a fissile nucleus helps to maintain reactivity
despite the consumption of 239Pu, and for this reason, plutonium with a high content of 240Pu
has been termed phoenix fuel
.