{"product_id":"nuclear-reactor-physics-and-engineering-isbn-9781394283552","title":"Nuclear Reactor Physics and Engineering","description":"\u003cp\u003e\u003cb\u003eEssential guide to analyzing nuclear energy systems, with focus on reactor physics, fuel cycle, system dynamics, thermal-hydraulics, and economics.\u003c\/b\u003e \u003c\/p\u003e\u003cp\u003e\u003ci\u003eNuclear Reactor Physics and Engineering\u003c\/i\u003e highlights efforts in utilizing low enrichment uranium fuel as a substitute for carbon-based fuels in energy generation and provides an overview of important aspects of nuclear reactor physics utilizing the neutron diffusion equation for major reactor designs and MATLAB software for system analysis, with exercises illustrating key points and design parameters as supplementary material. \u003c\/p\u003e\u003cp\u003eThis revised and updated Second Edition reflects key findings of the 2023 National Academy of Sciences (NAS) report and discusses physical and engineering characteristics of advanced nuclear reactors, especially in the form of small modular reactors that have the potential to provide enhanced safety and economics, as well as effective long-term management of used nuclear fuel in geological repositories. \u003c\/p\u003e\u003cp\u003eKey topics explored in the updated edition of \u003ci\u003eNuclear Reactor Physics and Engineering\u003c\/i\u003e include: \u003c\/p\u003e\u003cul\u003e\n\u003cli\u003eImpact of the use of high-assay low enrichment uranium (HALEU) fuel as a new efficient nuclear fuel\u003c\/li\u003e\n\u003cli\u003eAdvantages resulting from combined uses of light water reactor and sodium-cooled fast reactor with fuel reprocessing\u003c\/li\u003e\n\u003cli\u003eFundamental nuclear reactor physics, nuclear reactor system analysis, and lattice physics analysis for reactor cores \u003c\/li\u003e\n\u003cli\u003eNuclear fuel cycle analysis, nuclear plant simulation and control, and management of used nuclear fuel\u003c\/li\u003e\n\u003cli\u003eEconomic analysis of nuclear electricity and thermal-hydraulic analysis of nuclear systems.\u003c\/li\u003e\n\u003c\/ul\u003e \u003cp\u003eWith a wealth of all-new information detailing the state of the art in the field, \u003ci\u003eNuclear Reactor Physics and Engineering\u003c\/i\u003e is an invaluable reference on the subject for undergraduate and graduate students in nuclear engineering, as well as practicing engineers involved with nuclear power plants. \u003c\/p\u003e\u003cp\u003eList of Tables xv\u003c\/p\u003e \u003cp\u003eList of Figures xvii\u003c\/p\u003e \u003cp\u003ePreface xxix\u003c\/p\u003e \u003cp\u003ePreface to the Second Edition xxxi\u003c\/p\u003e \u003cp\u003ePermissions and Copyrights xxxiii\u003c\/p\u003e \u003cp\u003eAbout the Companion Website xxxv\u003c\/p\u003e \u003cp\u003e\u003cb\u003e1 Nuclear Power Plants 1\u003c\/b\u003e\u003c\/p\u003e \u003cp\u003e1.1 History and Current Status of Nuclear Power Plants 1\u003c\/p\u003e \u003cp\u003e1.2 Basic Features of Nuclear Power Plants 3\u003c\/p\u003e \u003cp\u003e1.3 Pressurized Water Reactor Systems 4\u003c\/p\u003e \u003cp\u003e1.4 Boiling Water Reactor Systems 10\u003c\/p\u003e \u003cp\u003e1.5 Advanced Reactor Designs 17\u003c\/p\u003e \u003cp\u003eReferences 30\u003c\/p\u003e \u003cp\u003eProblems 32\u003c\/p\u003e \u003cp\u003e\u003cb\u003e2 Neutron–Nucleus Reaction and Neutron Cross Section 33\u003c\/b\u003e\u003c\/p\u003e \u003cp\u003e2.1 Neutron–Nucleus Reaction Probability and Neutron Cross Section 34\u003c\/p\u003e \u003cp\u003e2.2 Mechanisms of Neutron–Nucleus Interaction 35\u003c\/p\u003e \u003cp\u003e2.3 Nuclear Fission Process 38\u003c\/p\u003e \u003cp\u003e2.4 Two-Body Collision Mechanics and Center-of-Mass System 44\u003c\/p\u003e \u003cp\u003e2.5 Single-Level Breit–Wigner Formula for Resonance Reaction 48\u003c\/p\u003e \u003cp\u003e2.6 Differential Scattering Cross Section and Scattering Kernel 51\u003c\/p\u003e \u003cp\u003e2.7 Further Remarks on Neutron Cross Section 55\u003c\/p\u003e \u003cp\u003eReferences 60\u003c\/p\u003e \u003cp\u003eProblems 61\u003c\/p\u003e \u003cp\u003e\u003cb\u003e3 Neutron Flux, Reaction Rate, and Effective Cross Section 65\u003c\/b\u003e\u003c\/p\u003e \u003cp\u003e3.1 Neutron Flux and Current 66\u003c\/p\u003e \u003cp\u003e3.2 Rate of Neutron–Nucleus Interaction 72\u003c\/p\u003e \u003cp\u003e3.3 Neutron Energy Distribution and Effective Thermal Cross Section 75\u003c\/p\u003e \u003cp\u003e3.4 Application to a 1∕V-Absorber 79\u003c\/p\u003e \u003cp\u003eReferences 80\u003c\/p\u003e \u003cp\u003eProblems 80\u003c\/p\u003e \u003cp\u003e\u003cb\u003e4 Derivation of the Neutron Diffusion Equation 83\u003c\/b\u003e\u003c\/p\u003e \u003cp\u003e4.1 Basic Assumptions for Neutron Balance Statement 84\u003c\/p\u003e \u003cp\u003e4.2 Neutron Balance Equation 85\u003c\/p\u003e \u003cp\u003e4.3 Neutron Source Term 89\u003c\/p\u003e \u003cp\u003e4.4 Fick’s Law of Neutron Current 90\u003c\/p\u003e \u003cp\u003e4.5 Neutron Transport Equation and \u003ci\u003eP\u003c\/i\u003e\u003csub\u003e1\u003c\/sub\u003e Approximation 93\u003c\/p\u003e \u003cp\u003e4.6 Remarks on Diffusion Coefficient 98\u003c\/p\u003e \u003cp\u003e4.7 Limitations of Neutron Diffusion Theory 100\u003c\/p\u003e \u003cp\u003e4.8 One-Group Neutron Diffusion Equation 100\u003c\/p\u003e \u003cp\u003e4.9 Summary Discussion of Diffusion Equation 102\u003c\/p\u003e \u003cp\u003eReferences 102\u003c\/p\u003e \u003cp\u003eProblems 103\u003c\/p\u003e \u003cp\u003e\u003cb\u003e5 Applications of the One-Group Neutron Diffusion Equation 105\u003c\/b\u003e\u003c\/p\u003e \u003cp\u003e5.1 Boundary Conditions for Diffusion Equation 106\u003c\/p\u003e \u003cp\u003e5.2 Solution of Steady-State Diffusion Equation 110\u003c\/p\u003e \u003cp\u003e5.3 Neutron Flux in Multiplying Medium and Criticality Condition 120\u003c\/p\u003e \u003cp\u003e5.4 Four- and Six-Factor Formulas for Multiplication Factor 129\u003c\/p\u003e \u003cp\u003e5.5 Concluding Remarks 131\u003c\/p\u003e \u003cp\u003eReferences 131\u003c\/p\u003e \u003cp\u003eProblems 132\u003c\/p\u003e \u003cp\u003e\u003cb\u003e6 Numerical Solution of the Neutron Diffusion Equation 137\u003c\/b\u003e\u003c\/p\u003e \u003cp\u003e6.1 Finite Difference Form of Diffusion Equation 138\u003c\/p\u003e \u003cp\u003e6.2 Flux Solution Algorithm: Inner Iteration 142\u003c\/p\u003e \u003cp\u003e6.3 Boundary Conditions for Difference Equation 144\u003c\/p\u003e \u003cp\u003e6.4 Source or Outer Iteration 146\u003c\/p\u003e \u003cp\u003e6.5 Relative Power Distribution and Overall Flow Chart 148\u003c\/p\u003e \u003cp\u003e6.6 Single-Channel Flux Synthesis 151\u003c\/p\u003e \u003cp\u003e6.7 Multidimensional Finite Difference Formulation 154\u003c\/p\u003e \u003cp\u003e6.8 Coarse-Mesh Diffusion Equation Solver 160\u003c\/p\u003e \u003cp\u003e6.9 Krylov Subspace Method as a Diffusion Equation Solver 164\u003c\/p\u003e \u003cp\u003eReferences 168\u003c\/p\u003e \u003cp\u003eProblems 169\u003c\/p\u003e \u003cp\u003e\u003cb\u003e7 Applications of the Two-Group Neutron Diffusion Equation 171\u003c\/b\u003e\u003c\/p\u003e \u003cp\u003e7.1 Derivation of Multigroup Neutron Diffusion Equation 172\u003c\/p\u003e \u003cp\u003e7.2 Steady-State Multigroup Diffusion Equation 176\u003c\/p\u003e \u003cp\u003e7.3 Two-Group Form of Effective Multiplication Factor 178\u003c\/p\u003e \u003cp\u003e7.4 General Two-Group Diffusion Analysis 181\u003c\/p\u003e \u003cp\u003eReferences 184\u003c\/p\u003e \u003cp\u003eProblems 184\u003c\/p\u003e \u003cp\u003e\u003cb\u003e8 Nuclear Reactor Kinetics 189\u003c\/b\u003e\u003c\/p\u003e \u003cp\u003e8.1 Derivation of Point Kinetics Equation 190\u003c\/p\u003e \u003cp\u003e8.2 Solution of Point Kinetics Equation without Feedback 194\u003c\/p\u003e \u003cp\u003e8.3 State Space Representation of Point Kinetics Equation 205\u003c\/p\u003e \u003cp\u003e8.4 Point Kinetics Equation with Feedback 208\u003c\/p\u003e \u003cp\u003e8.5 Reactivity Measurements 214\u003c\/p\u003e \u003cp\u003e8.6 System Stability Analysis 217\u003c\/p\u003e \u003cp\u003e8.7 Point Reactor and Space-Dependent Reactor Kinetics 221\u003c\/p\u003e \u003cp\u003eReferences 223\u003c\/p\u003e \u003cp\u003eProblems 223\u003c\/p\u003e \u003cp\u003e\u003cb\u003e9 Fast Neutron Spectrum Calculation 227\u003c\/b\u003e\u003c\/p\u003e \u003cp\u003e9.1 Neutron Balance Equation and Slowing Down Density 228\u003c\/p\u003e \u003cp\u003e9.2 Elastic Scattering and Lethargy Variable 232\u003c\/p\u003e \u003cp\u003e9.3 Neutron Slowing Down in Infinite Medium 234\u003c\/p\u003e \u003cp\u003e9.4 Resonance Escape Probability 243\u003c\/p\u003e \u003cp\u003e9.5 Doppler Broadening of Resonances 250\u003c\/p\u003e \u003cp\u003e9.6 Fermi Age Theory 256\u003c\/p\u003e \u003cp\u003e9.7 Comments on Lattice Physics Analysis 260\u003c\/p\u003e \u003cp\u003eReferences 261\u003c\/p\u003e \u003cp\u003eProblems 262\u003c\/p\u003e \u003cp\u003e\u003cb\u003e10 Perturbation Theory and Adjoint Flux 265\u003c\/b\u003e\u003c\/p\u003e \u003cp\u003e10.1 Operator Notation for Neutron Diffusion Equation 265\u003c\/p\u003e \u003cp\u003e10.2 Adjoint Operator and Adjoint Flux 267\u003c\/p\u003e \u003cp\u003e10.3 First-Order Perturbation Theory 269\u003c\/p\u003e \u003cp\u003e10.4 Adjoint Flux for Control Rod Worth Calculation 271\u003c\/p\u003e \u003cp\u003e10.5 Adjoint Flux for Variational Formulation 273\u003c\/p\u003e \u003cp\u003e10.6 Adjoint Flux for Detector Response Calculation 274\u003c\/p\u003e \u003cp\u003e10.7 Adjoint Formulation for Flux Perturbation Calculation 276\u003c\/p\u003e \u003cp\u003e10.8 Concluding Remarks on Adjoint Flux 280\u003c\/p\u003e \u003cp\u003eReferences 280\u003c\/p\u003e \u003cp\u003eProblems 281\u003c\/p\u003e \u003cp\u003e\u003cb\u003e11 Lattice Physics Analysis of Heterogeneous Cores 283\u003c\/b\u003e\u003c\/p\u003e \u003cp\u003e11.1 Material Heterogeneity and Flux Distribution in Unit Cell 285\u003c\/p\u003e \u003cp\u003e11.2 Neutronic Advantages of Fuel Lumping 287\u003c\/p\u003e \u003cp\u003e11.3 Diffusion Theory Model for Thermal Utilization 291\u003c\/p\u003e \u003cp\u003e11.4 Improved Method for Thermal Disadvantage Factor 296\u003c\/p\u003e \u003cp\u003e11.5 Resonance Escape Probability for Heterogeneous Cell 300\u003c\/p\u003e \u003cp\u003e11.6 Thermal Spectrum Calculation 310\u003c\/p\u003e \u003cp\u003e11.7 Integral Transport Methods 313\u003c\/p\u003e \u003cp\u003e11.8 \u003ci\u003eB\u003c\/i\u003e\u003csub\u003e1\u003c\/sub\u003e Formulation for Spectrum Calculation 316\u003c\/p\u003e \u003cp\u003e11.9 Lattice Physics Methodology for Fast Reactor 322\u003c\/p\u003e \u003cp\u003e11.10 Monte Carlo Lattice Physics Analysis 325\u003c\/p\u003e \u003cp\u003e11.11 Overall Reactor Physics Analysis 326\u003c\/p\u003e \u003cp\u003eReferences 327\u003c\/p\u003e \u003cp\u003eProblems 330\u003c\/p\u003e \u003cp\u003e\u003cb\u003e12 Nuclear Fuel Cycle Analysis and Management 333\u003c\/b\u003e\u003c\/p\u003e \u003cp\u003e12.1 Nuclear Fuel Cycle Analysis 334\u003c\/p\u003e \u003cp\u003e12.2 Nuclear Transmutation Formulation 337\u003c\/p\u003e \u003cp\u003e12.3 Equilibrium Cycle and Mass Balance 347\u003c\/p\u003e \u003cp\u003e12.4 Simplified Cycling Model 353\u003c\/p\u003e \u003cp\u003e12.5 Fission Product Xenon Buildup 359\u003c\/p\u003e \u003cp\u003e12.6 General Incore Management Considerations 365\u003c\/p\u003e \u003cp\u003e12.7 Fission Products and Radioactive Waste 371\u003c\/p\u003e \u003cp\u003e12.8 Management of Used Nuclear Fuel 376\u003c\/p\u003e \u003cp\u003e12.9 Key Considerations for Geological Disposal 396\u003c\/p\u003e \u003cp\u003eReferences 404\u003c\/p\u003e \u003cp\u003eProblems 409\u003c\/p\u003e \u003cp\u003e\u003cb\u003e13 Thermal-Hydraulic Analysis of Reactor Systems 413\u003c\/b\u003e\u003c\/p\u003e \u003cp\u003e13.1 Empirical Laws for Energy and Momentum Transport 415\u003c\/p\u003e \u003cp\u003e13.2 Derivation of Fluid Conservation Equations 418\u003c\/p\u003e \u003cp\u003e13.3 Simple Solutions of Fluid Conservation Equations 426\u003c\/p\u003e \u003cp\u003e13.4 Conservation Equations for Channel Flow 443\u003c\/p\u003e \u003cp\u003e13.5 Axial Temperature Distribution in Reactor Core 446\u003c\/p\u003e \u003cp\u003e13.6 Boiling Heat Transfer and Two-Phase Flow 456\u003c\/p\u003e \u003cp\u003e13.7 Thermal Hydraulic Limitations and Power Capability 471\u003c\/p\u003e \u003cp\u003e13.8 Thermal-Hydraulic Models for Nuclear Plant Analysis 479\u003c\/p\u003e \u003cp\u003e13.9 Advances in Nuclear Plant Modeling System 488\u003c\/p\u003e \u003cp\u003eReferences 489\u003c\/p\u003e \u003cp\u003eProblems 493\u003c\/p\u003e \u003cp\u003e\u003cb\u003e14 Power Coefficients of Reactivity 499\u003c\/b\u003e\u003c\/p\u003e \u003cp\u003e14.1 Physical Phenomena Affecting Core Reactivity 500\u003c\/p\u003e \u003cp\u003e14.2 Relationship Between Reactivity Coefficients 502\u003c\/p\u003e \u003cp\u003e14.3 Two-Group Representation of Reactivity Feedback 503\u003c\/p\u003e \u003cp\u003e14.4 Parametric Dependence of LWR Reactivity Coefficients 505\u003c\/p\u003e \u003cp\u003e14.5 Reactivity Coefficients in Sodium-Cooled Fast Reactor 508\u003c\/p\u003e \u003cp\u003e14.6 Reactivity Feedback Model for Sodium-Cooled Fast Reactor 510\u003c\/p\u003e \u003cp\u003eReferences 512\u003c\/p\u003e \u003cp\u003eProblems 513\u003c\/p\u003e \u003cp\u003e\u003cb\u003e15 Nuclear Energy Economics 515\u003c\/b\u003e\u003c\/p\u003e \u003cp\u003e15.1 Electrical Energy Cost 516\u003c\/p\u003e \u003cp\u003e15.2 Overview of Engineering Economics 519\u003c\/p\u003e \u003cp\u003e15.3 Calculation of Nuclear Electricity Generation Cost 521\u003c\/p\u003e \u003cp\u003e15.4 Impact of Increased Capital and O\u0026amp;M Costs 530\u003c\/p\u003e \u003cp\u003e15.5 Energy Generation Efficiency of Various Technologies 533\u003c\/p\u003e \u003cp\u003eReferences 536\u003c\/p\u003e \u003cp\u003eProblems 539\u003c\/p\u003e \u003cp\u003e\u003cb\u003e16 Space-Time Kinetics and Reactor Control 541\u003c\/b\u003e\u003c\/p\u003e \u003cp\u003e16.1 Space-Time Reactor Kinetics 542\u003c\/p\u003e \u003cp\u003e16.2 Space-Time Power Oscillations due to Xenon Poisoning 551\u003c\/p\u003e \u003cp\u003e16.3 Time-Optimal Reactor Control 564\u003c\/p\u003e \u003cp\u003e16.4 Model-Based Reactor Control 572\u003c\/p\u003e \u003cp\u003e16.5 Alternate Reactor Control Techniques 581\u003c\/p\u003e \u003cp\u003e16.6 Kalman Filtering for Optimal System Estimation 585\u003c\/p\u003e \u003cp\u003eReferences 588\u003c\/p\u003e \u003cp\u003eProblems 592\u003c\/p\u003e \u003cp\u003e\u003cb\u003e17 Elements of Neutron Transport Theory 595\u003c\/b\u003e\u003c\/p\u003e \u003cp\u003e17.1 Collision Probability Method 595\u003c\/p\u003e \u003cp\u003e17.2 First-Flight Escape Probability and Dirac Chord Method 600\u003c\/p\u003e \u003cp\u003e17.3 Flux Depression Calculation and Blackness 605\u003c\/p\u003e \u003cp\u003e17.4 Numerical Solution of Neutron Transport Equation 610\u003c\/p\u003e \u003cp\u003eReferences 621\u003c\/p\u003e \u003cp\u003eProblems 623\u003c\/p\u003e \u003cp\u003e\u003cb\u003eAppendix A Key Physical Constants 627\u003c\/b\u003e\u003c\/p\u003e \u003cp\u003e\u003cb\u003eAppendix B Comparison of Major Reactor Types 629\u003c\/b\u003e\u003c\/p\u003e \u003cp\u003eReferences 633\u003c\/p\u003e \u003cp\u003e\u003cb\u003eAppendix C Special Mathematical Functions 635\u003c\/b\u003e\u003c\/p\u003e \u003cp\u003eC.1 Gamma Function 635\u003c\/p\u003e \u003cp\u003eC.2 Legendre Polynomial and Spherical Harmonics 637\u003c\/p\u003e \u003cp\u003eC.3 Bessel Function 639\u003c\/p\u003e \u003cp\u003eC.4 Dirac Delta Function 642\u003c\/p\u003e \u003cp\u003eReferences 642\u003c\/p\u003e \u003cp\u003e\u003cb\u003eAppendix D Integral Transforms 643\u003c\/b\u003e\u003c\/p\u003e \u003cp\u003eD.1 Laplace Transform 643\u003c\/p\u003e \u003cp\u003eD.2 Fourier Transform 645\u003c\/p\u003e \u003cp\u003eD.3 Jordan’s Lemma 645\u003c\/p\u003e \u003cp\u003eReferences 647\u003c\/p\u003e \u003cp\u003e\u003cb\u003eAppendix E Calculus of Variation for Optimal Control Formulation 649\u003c\/b\u003e\u003c\/p\u003e \u003cp\u003eE.1 Euler–Lagrange and Hamilton Equations 649\u003c\/p\u003e \u003cp\u003eE.2 Pontryagin’s Maximum Principle 650\u003c\/p\u003e \u003cp\u003eReferences 656\u003c\/p\u003e \u003cp\u003e\u003cb\u003eAppendix F Kalman Filter Algorithm 657\u003c\/b\u003e\u003c\/p\u003e \u003cp\u003eF.1 Linear Kalman Filter 657\u003c\/p\u003e \u003cp\u003eF.2 Unscented Kalman Filter 660\u003c\/p\u003e \u003cp\u003eReferences 662\u003c\/p\u003e \u003cp\u003eAnswers to Selected Problems 663\u003c\/p\u003e \u003cp\u003eIndex 679\u003c\/p\u003e  \u003cp\u003e\u003cb\u003eJohn C. Lee, PhD,\u003c\/b\u003e has been on the nuclear engineering faculty at the University of Michigan since 1974 and served as the department chair for six years. He has published two Wiley books, \u003ci\u003eRisk and Safety Analysis of Nuclear Systems\u003c\/i\u003e (with N.J. McCormick, 2011, 2017 second printing) and \u003ci\u003eNuclear Reactor Physics and Engineering\u003c\/i\u003e (2020). He has served on two U.S. National Academy of Sciences committees, including the recent committee on advanced nuclear reactors and used nuclear fuel. Dr. Lee is a Fellow of the American Nuclear Society.   \u003c\/p\u003e\u003cp\u003e\u003cb\u003eEssential guide to analyzing nuclear energy systems, with focus on reactor physics, fuel cycle, system dynamics, thermal-hydraulics, and economics.\u003c\/b\u003e \u003c\/p\u003e\u003cp\u003e\u003ci\u003eNuclear Reactor Physics and Engineering\u003c\/i\u003e highlights efforts in utilizing low enrichment uranium fuel as a substitute for carbon-based fuels in energy generation and provides an overview of important aspects of nuclear reactor physics utilizing the neutron diffusion equation for major reactor designs and MATLAB software for system analysis, with exercises illustrating key points and design parameters as supplementary material. \u003c\/p\u003e\u003cp\u003eThis revised and updated Second Edition reflects key findings of the 2023 National Academy of Sciences (NAS) report and discusses physical and engineering characteristics of advanced nuclear reactors, especially in the form of small modular reactors that have the potential to provide enhanced safety and economics, as well as effective long-term management of used nuclear fuel in geological repositories. \u003c\/p\u003e\u003cp\u003eKey topics explored in the updated edition of \u003ci\u003eNuclear Reactor Physics and Engineering\u003c\/i\u003e include: \u003c\/p\u003e\u003cul\u003e\n\u003cli\u003eImpact of the use of high-assay low enrichment uranium (HALEU) fuel as a new efficient nuclear fuel\u003c\/li\u003e\n\u003cli\u003eAdvantages resulting from combined uses of light water reactor and sodium-cooled fast reactor with fuel reprocessing\u003c\/li\u003e\n\u003cli\u003eFundamental nuclear reactor physics, nuclear reactor system analysis, and lattice physics analysis for reactor cores \u003c\/li\u003e\n\u003cli\u003eNuclear fuel cycle analysis, nuclear plant simulation and control, and management of used nuclear fuel\u003c\/li\u003e\n\u003cli\u003eEconomic analysis of nuclear electricity and thermal-hydraulic analysis of nuclear systems.\u003c\/li\u003e\n\u003c\/ul\u003e \u003cp\u003eWith a wealth of all-new information detailing the state of the art in the field, \u003ci\u003eNuclear Reactor Physics and Engineering\u003c\/i\u003e is an invaluable reference on the subject for undergraduate and graduate students in nuclear engineering, as well as practicing engineers involved with nuclear power plants.\u003c\/p\u003e","brand":"Wiley","offers":[{"title":"Default Title","offer_id":47989701837029,"sku":"NP9781394283552","price":140.95,"currency_code":"USD","in_stock":false}],"thumbnail_url":"\/\/cdn.shopify.com\/s\/files\/1\/1842\/7735\/files\/9781394283552.jpg?v=1761785166","url":"https:\/\/k12savings.com\/es\/products\/nuclear-reactor-physics-and-engineering-isbn-9781394283552","provider":"K12savings","version":"1.0","type":"link"}